O.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8510160151 DOC ~ DATE: 85/10/11 NOTARIZED:.NOFACIL'.50 275, Diablo Canyon Nuclear Power- Pl anti, Unit» 1~ Pac) fic'a

50 323 Diablo Canyon Nuclear Power Plant~ Unit 2i Pacific GaAUTH'eNAME" AUTHOR-'FFILIATION

SHIFFERi J>,O; Pacific Gas 8 Electric Co,RECIP ~ NAt1El RECIPIENT AFFILIATION

KNIGHTONiGe H, Licensing Branch 3

SUBJECT; Informs of- review completion of -inservice testing programdocumented in SSER 31.Further discussions required toclarify NRC evaluations of Items 3<0 L.13 in Section5<2',8. 1,Meeting, requested for 851104-05 in BethesdaiMO,

DISTRIBUTION CODE ~ A047D COPIES RECE'>I>CO L>TR "ENCL " SIZE ~

TITLE: OR Submittal; Inservice Inspection/Testing

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PA.CIFIC GA.S A.ND ELECTS,IC COMPA.NT77 BEAlE STREET ~ SAN FRANCISCO, CAI.IFORNIA94106 ~ (415) 781 4211 ~ TWX 910 372 6587

JAMES D. SHIFFKRVICC PR55IDINT

NVCLCAR POW5R G5N5RATION October ll, 1985

PGandE Letter Ho.: DCL-85-320

Mr. George W. Knighton, ChiefLicensing Branch No. 3Division of LicensingOffice of Nuclear Reactor RegulationU.'. Nuclear Regulatory CommissionWashington, D.C. 20555

Re: Docket No. 50-275, OL-DPR-80Docket No. 50-323, OL-DPR-82Diablo Canyon Units 1 and 2Inservice Testing Program

Dear Mr. Knighton:

PGandE has reviewed the NRC Staff's evaluation of the Diablo Canyon InserviceTesting ( IST) Program documented in SSER 31. As a result of our review,PGandE believes that further discussions are required to clarify the NRC

Staff's evaluation of items 3, 4 and 13 in Section 5.2.8.1 of SSER 31 whichaddress pump vibration measurement, pump flow measurement, and categorizationof check valves in the emergency core cooling system. Regarding item 13,PGandE's basis for classifying certain check valves is provided in theenclosure.

As discussed with the HRC Project Manager, PGandE requests a meeting on

items 3, 4 and 13 at Bethesda on November 4 and 5, 1985.

Kindly acknowledge receipt of this material on the enclosed copy of thisletter and return it in the enclosed addressed envelope.

Sincerely,

g CJ. D. Shiffer

Enclosure

cc: L. Chandler 8510160151 85101J. B. Martin ', "DR ADOCK 05pppp75B. Norton -- -- -- -'.= PDR

H. E. SchierlingCPUCDiablo Distribution

0561 S/0037K/J HA/469

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PGandE ter No.: DCL-85-320

ENCLOSURE

EMERGENCY CORE COOLING SYSTEM CHECK YALVES

The NRC Staff's evaluation of the Diablo Canyon Inservice Testing (IST)Program is documented in SSER 31. Item 13 in Section 5.2.8.1 of SSER 31

addresses the categorization of check valves in the emergency core coolingsystem (ECCS); specifically, (1) safety injection to hot legs second-off checkvalves 8905A, B, C and D, and (2) residual heat removal to hot legs second-offcheck valves 8740A and B. The NRC's evaluation of these check valves isprovided below with PGandE's basis for not reclassifying the valves.

NRC Evaluation ( Item 13: SSER 31, . 5-6, 5-7)

"PGandE has classified certain check valves in the safety injection system andthe residual heat removal system, which perform a pressure boundary isolationfunction, as Category C valves. These systems, which are connected to thereactor coolant pressure boundary, have design pressures that are below thereactor coolant system operating pressure. The redundant isolation checkvalves are within the ASME Section III, Class 1 boundary forming an interfacebetween the high and low pressure systems and protect the low pressure systemsfrom pressures that exceed their design limit. In this role, the check valvesperform a pressure isolation function. The staff considers the redundantisolation provided by these check valves to be an important safety functionand therefore it is necessary to assure the condition of each check valve isadequate to maintain the redundant isolation capability.

Accordingly, the following check valves in the safety injection system and theresidual heat removal system shall be reclassified valve category A/C andtested in accordance with Technical Specification 4.4.6.2.2 and included inTable 3.4-1 of the Technical Specifications. These check valves are:

Safety Injection System (SI)8905A SI to hot leg-l, 8905B SI to hot leg-2,8905C SI to hot leg-3, and 8905D SI to hot leg-4.

Residual Heat Removal System (RHR)8740A RHR to hot leg-l, and 8740B RHR to hot leg-2."

PGandE Discussion

As clarified in discussions with the NRC Staff, the Diablo Canyon systemdesign configuration shows that these check valves do not form an interfacebetween high and low pressure systems. The attached FSAR Update figuresprovide the piping schematics for the safety injection system and the residualheat removal system. These schematics show that, in both cases, the upstreamand downstream piping classification is S6, which is nominally rated at 2500psia. The valves that form the interface between the high and low pressuresystems are one valve further upstream in the systems'low path, i.e., valves8802A and B for the safety injection system and valve 8703 for the residualheat removal system.

0561S/0037K

During plant operation, routine performance of Technical SpecificationSurveillance Requirement 4. 5. 2 once per shift ensures that valves 8802A,8802B, and 8703 are closed with the power to their valve operators removed.With power removed, inadvertant operation of these valves is not possible and

accidental overpressurization of the safety injection and residual heatremoval systems is prevented. t

Since check valves 8905A, B, C and D and 8740A and B do not perform a pressureboundary isolation function, and administrative controls are in place toprevent overpressurization of the safety injection and residual heat removalsystems, it is not necessary to reclassify these valves as Category A/C asstated in SSER 31. For the same reasons, these valves require neither testingin accordance with Technical Specification 4.4.6.2.2 nor inclusion into Table3.4-1 of the Technical Specifications.

Attachments: FSAR Update Figure 3.2-09, Sheet 5 (Piping Schematic - SafetyInjection System)

FSAR Update Figure 3.2-10, Sheet 1 (Piping Schematic - ResidualHeat Removal System)

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