ML18022A424

Forwards Rev 3 to Vol 6,Part 7 of Inservice Insp Program ISI-203, ASME Section XI Pump & Valve Program Plan, for Inservice Testing

ML18022A424
Person / Time
Site:	Harris
Issue date:	09/16/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML18022A425	List: ML18022A424 ML18022A426
References
NLS-86-339, NUDOCS 8609220345
Download: ML18022A424 (5)

Text

R. LA. RY INFORNATION DISTR 1 t'I BYSTEl'1 (R IDB)

ACCESSION NBR: 8609220345 DOC. DATE: 86/09/i6 NOTARIZED: NO DOCKET ¹ FACIL: 50-400 Shearon Harris Nuclear Power Plant> Unit i> Carolina 05000400 AUTH. NANE AUTHOR AFFILXATIGN ZXNl'lERiMN>B. R. Carolina Power 8c Light Co.

RECIP. NANE RECIPIENT AFFILIATION DENTON> H. R. Office of Nuclear Reactor Regulation> Director (post 85ii25 BUXt JECT:

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Forwards Rev 3 to Vol 6> Par t 7 of Inservice Insp Program ISI-203> "ASNE Section XI Pump 5 Valve Program Plan> " for inserv i c e testing.

TITLE: Licensing CODE: BOOID COPIEB, RECEIVED:

Submittal: PSAR/FSAR Amdts LTR 8<

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Related Correspondence 8-5 9'ISTRIBUTION NOTES: Application for permit renewal wiled. 05000400 RECIPIENT COPIEB RECIPIENT COPIES ID CODE/NANE LTTR ENCL ID CODE/NAi>>E LTTR ENCL P>AR-A EB PMR-A EICSB PHR-A FOB } PWR-A PD2 LA PNR-A PD2 PD PNR-A PSB i+ HUCKLEY> 8 PMR-A RBB Oi INTERNAL ADN/LFNB ELD/HDBi XE FILE IE/DEPER/EPH 36 IE/DGAVT/GAB 2i NRR BWR ADTB NRR PNR-9 ADTS N NRR/DHFT/ltTB FILE L'EG RCN2 NIB EXTERNAL: 9NL(Al"}DTB ONLY) i 0 DNB/DSB (AMDTS)

LPDR 03 NRC .PDR 02 NBIC 05 1+ PNL ('RUEL> R gncS TOTAL NUl'tBER OF COPXES REQUIRED: LTTR 30 ENCL

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Carolina Power & LIght Company SERIAL: NLS-86-339 SEP 16 m Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 - DOCKET NO.50-000 IN-SERVICE PUMP AND VALVE TESTING PROGRAM Dear Mr. Denton Carolina Power R Light (CPRL) hereby submits for your review, Revision 3 of the Shearon Harris Nuclear Power Plant (SHNPP) Program Plan for In-Service Testing of Pumps and Valves. This revision supersedes and replaces Revision 1, as submitted 3anuary 27, 1986 (NLS-85-350), and FSAR Appendix 3.9D in their entirety.

The program plan has been revised to accommodate additional information identified during the preparation of procedures, plant modifications, etc. Included in the revision is resolution of comments resulting from the NRC staff review of Revision I (see CPRL letter dated 3uly 31, 1986, NLS-86-262 in response to a NRC Staff Request for additional information). Also included are changes resulting from discussion during the August 5 and 6, 1986 meeting with your staff. Note that due to time constraints, the items discussed in an August 29 phone conversation have not been addressed. They will be addressed in a future revision and they do not degrade the effectiveness of the program on an interim basis.

The SHNPP Inservice Pump and Valve Testing Program is in the form of a plant procedure (ISI-203). Major changes from Revision 1 include refor mating to facilitate a logical and expeditious review of the material. The revised program plan is being submitted to provide the most up-to-date information in support of the overall licensing process. The in-service pump and valve testing program is addressed in Section 3.9.6 of the SER (NUREG-1038). The attached revision of the program is consistent with the SER as currently written.

Generally, the staff's comments have been accommodated in the program plan changes.

Areas where CPrtrL maintains previously stated positions include:

~ Testin of Check Valves in Series Relief requests have been incorporated in Revision 3 to exempt these series check valves from individual valve verification of reverse flow closure.

Auxiliar Feedwater S stem Valves IAF-50, 73, 92, 117, 136, 102, and 108 Item D. 1 >>

Each flow path from the auxiliary feedwater pumps to the feedwater lines includes two check valves in series. Each two check valve set functions as a single unit to prevent reverse flow from the reedwater lines back through the pumps. Reverse +sots I

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411 Fayettevilte Street < P. O. Box 1551 o Raleigh. N. C. 27602 8b09220345 8b09ib PDR ADOCK 05000400 8 PDR

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flow is prevented as long as either check valve is closed. Each line is continuously monitored by alarmed temperature sensors. Thus, if both valves fail to close an over-temperature alarm will occur. CPRL maintains that the lack of an alarm verifies that at least one of the series valves is closed and that their design function is being accomplished. If an over-temperature alarm indicated failure to close, the appropriate valves will be identified and corrective action initiated.

Com onent Coolin Water S stem Valves 1CC-118 and 119 (Item O.l~)

Of these back-to-back check valves, only one is required to isolate the nonclassed sampling system from the CCW. If either valve closes on flow reversal, system requirements are satisfied. The second valve has been installed as a backup to the safety-related valve as an operating convenience. Testing the two valves as a unit is equivalent to testing a single check valve in this location. Since only one of the two valves is required to close and because there are no system provisions for individual valve closure verification, they will be tested as a unit and if the unit fails to exhibit reverse flow closure, both valves will be disassembled 'and repaired.

~ Safet Classification of LTOP's (Item N.5~)

CPRL maintains that the check valves in the nitrogen supply to the PORV accumulators are not safety related and, therefore, are not included in the program.

~ Diesel Generator Air Start Valves (Item I.I+)

CPRL maintains that these valves are located on the diesel generator skid-mounted package and are outside the scope of Section XI testing. They are adequately tested during diesel generator testing.

<<See specific items in CPRL's response to Requested Additional Information dated 3uly 31, 1986 (NLS-86-262).

If you have any questions on this subject, please contact Mr. S. D. Chaplin at (919) 836-6623.

Yours very truly, S. R imme man an r Nuclear Licensing Section SDC/crs (0079SDC) cc: Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Dr. 3. Nelson Grace (NRC-Rll)