ML17285B179

Application for Amend to License NPF-21,revising Tech Spec Figure 3.4.6.1 Re Pressure/Temp Limits Curve

ML17285B179
Person / Time
Site:	Columbia
Issue date:	04/05/1990
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17285B180	List: ML17285B179 ML17285B181
References
GL-88-11, GO2-90-071, GO2-90-71, NUDOCS 9004200247
Download: ML17285B179 (5)

Text

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ACCELERATED DISTRIBUTION DEMONSHRATION SYSIEM l~ f REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9004200247 DOC.DATE: 90/04/05 NOTARIZED: YES DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document .Control Desk)

SUBJECT:

Application for amend to License NPF-21,reviseing Tech Spec figure 3.4.6.1.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5'D 1 1 SAMWORTH, R 5 5 INTERNAL: ACRS '

6 6 NRR/DET/ECMB 9H 1 1 NRR/DOEA/OTSB1 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 . 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC/LF 1 0 OGC/HDS2 1 0 RB P~E 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WAS'! CONTACT THE.DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISIRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED)

TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 25

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 April 5, 1990 G02-90-071 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 RE(UEST FOR AMENDMENT TO TECHNICAL SPECIFICATION PRESSURE/TEMPERATURE LIMITS - SECTION 3.4.6.1, SUPPLEMENTAL INFORMATION

References:

1) Letter, G02-89-201, GC Sorensen (SS) to NRC, same subject, dated October 27, 1989

2) Generic Letter 88-11, "NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations", dated July 12, 1988 Reference 1 submitted the subject technical specification in response to the reference 2 generic letter. In subsequent conversations between Messrs R.

Samworth and J. Tsao (NRC) and P. Powell, D. Bosi and T. Erwin (Supply System) it was recognized that the reactor pressure vessel temperature limit curves provided by Reference 1 as Figure 3.4.6. 1 did not encompass the conservatisms contemplated by the Staff. Accordingly, the attached pressure/temperature limits curve is submitted as replacement to that provided in Reference 1.

The Supply System's initial submittal of the reactor pressure vessel temperature limit curves was completed in strict compliance with Appendix G of the ASME Code, NUREG 0800, Regulatory Guide 1.99 Rev. 2, and WRC Bulletin 175. The attached revised curves incorporate further conservatism involving through-wall temperature corrections as suggested by the Staff. The normal startup/shutdown fluid temperatures conservatively follow the steam saturation line controlled by the turbine bypass valves above 130 psig. In sum, a high level of conservatism is imposed at WNP-2 when both operational guidelines and the technical specification limits, as specified by the revised pressure/temperature limit curves, are considered.

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<Page Two t RE(UEST FOR AMEND TO TS PRESSURE/TEMPERATURE LIMITS - SECTION 3.4.6. 1, SUPPLEMENTAL INFORMATION The Supply System has reviewed the No Significant Hazards and Environmental Assessment Exclusion discussions provided in reference 1 and concluded that these discussions bound the conservative changes represented in the attached curve.

This supplemental information has been reviewed and approved by the WNP-2 Plant Operations Committee (POC) and the Supply System Corporate Nuclear Safety Review Board (CNSRB). In accordance with 10CFR 50.91, the State of Washington has been provided a copy of this letter.

As stated in Reference 1 the generic letter requires implementation within two plant outages of the effective date of Revision 2 to Regulatory Guide 1.99 (May 1988). Accordingly, for WNP-2 this change should be effective no later than commencement of initial heat up at the end of the WNP-2 1990 refueling outage tentatively scheduled for May 31, 1990.

Very truly yours, G. C. Sorensen, Manager Regulatory Programs PLP/bk Attachments CC: JB Martin - NRC RV NS Reynolds - BCPER RB Samworth - NRC DL Will.iams - BPA/399 NRC Site Inspector - 901A

A'TATE Request for Amend. to TS Pressure/

OF WASHINGTON )

Subject:

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'OUNTY OF BENTON )

I, A. G. HOSLER, being duly sworn, subscribe to and say that I am the Manager, WNP-2 Licensing, for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant her ein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my -knowledge, information and belief the statements made in it are true.

OATE ~,. 5 1990 A. G. HOSLER, Manager WNP-2 Licensing On this day personally appeared before me A. G. HOSLER to me known to be the

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the foregoing instrument and acknowledged that he signed individual who executed the same as his free act and deed for the uses and purposes herein mentioned.

GIYEN under my hand and seal this day of ,1990.

u otary u ic in a d or t e State of Washington Residing at

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