ML20148C449

Safety Evaluation Supporting 850816,860606 & 871117 Relief Requests from ASME Boiler & Pressure Vessel Code,Section XI, Implemented in Plant on 820303 for First 10-yr Inservice Testing Program on Pumps & Valves

ML20148C449
Person / Time
Site:	Sequoyah
Issue date:	01/19/1988
From:	NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20147C326	List: ML20147C323 ML20148C278 ML20148C449
References
NUDOCS 8801250194
Download: ML20148C449 (3)

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$. $ WASHING TON, D. C, 20555 SAFETY EVALUATION BY THE OFFICE OF SPECIAL PROJECTS RELATING TO RElf EF FROM TFE ASME BOILER AND PRESSURE VESSEL CODE SECTION XI. "RULES FOR INSERVICE INSPECTION OF NUCLEAR POYER PLANT COMPONENTS - DIVISION I" TENhESSEE VALLEY AUTHORITY SEOU0YAH NUCLEAR PtANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328

1.0 INTRODUCTION

Section 50.55a, "Codes and Standards," of 10 CFR Part 50 recuires, in part, that certain safety-related pumps and valves meet the requirements of Section XI of the Anerican Society of Mechcr,' cal Engineers (ASME) Boiler and Pressure Vessel Code (hereafter "the Code"). In order to rtet the requirements of this regulation, the Tennessee Valley Authority (TVA) has submitted to the NRC its first ten-year Inservice lesting (IST) program on pumps and valves for the Sequoyah huclear Plart, Units 1 and 2 in its letter dated March 3, 1982.

The IST program for Sequoy3h was revised in loter submittals dated November 4, 1982, April 16,1984, Augus; 16,1985, June 6,1986, hovember 17, 1986, December 12, 1986. July 2, 1967. August 14, 1987 and November 17, 1987. In these letters, TVA requested relief from certain Code Section XI requirements for specific pumps and valves in the Sequoyah Units 1 and 2 IST program. The staff issued a Safety Evaluation (SE) concerning the Seouoyah IST progran en April 5,1985. This SE addressed the relief recuests in the three submittals dated March 3, 1982 to April 16, 1984 Subsequently, TVA proposed further program changes in its submittals dated August 16, 1985 to August 14, 1987 The staff was requested to first review the priority items requested by TVA to support the Seoucyah Unit 2 restart.

The staff issued a second SE on October 23, 1987 which was limited to 21 relief requests from the ASME Code,Section XI, that were identified by TVA as needing resolution prior to restart of the Sequoyah plant. The following evaluation addresses three remaining relief recuests identified in the August 16, 1985 and June 6, 1986 submittals, and one relief request which was submitted by letter dated Noven.ber 17, 1907 in response to an NRC Integrated Design inspection (101) finding and identified by TVA as needing resolution prior to the restart of Seauoyah Unit 2. In addition, a revision to a relief request previously reviewed in the staff's October 23, 1987 SE is addressed.

8801250194 890119 PDR ADOCK 05000327 0 PDR

L-4 Regulation 10 CFR 50.55a(g)(6)(1) authori:es the Conmission to grant relief from the requirements of the Code upon making the necessary findings and, pursuant to 10 CFR 50.55a(a)(3), the Conmission may authorize citernatives to the Ocde requirerents. This SE contains NPC staff findings with respect tn granting relief requests submitted as part of the licensee's IST program.

2.0 EVALUATION The NRC consultant, Oak Ridge National laboratory, has reviewed the licensee's five relief requests and prepared the attached Technical Evaluation Report (TER). The staff has reviewed the evaluation and concurs in, and adopts, its ,

bases and findings. The granting of relief is based upon the fulfillment of dny Commitments rade by the licensee in its basis for each relief request and the proposed alternate testing.

Relief has been granted from the testing recuirenents which the staff has determined to te impractical to perform, would not compromise the safety of the plant, and where testing if innlemented, would result in undue hardship, end by deterniration that the relief requests were evaluated in accordance with 10 CFR 50.55a(g)(6)(i). The following relief requests were determined to be acceptable:

1. Ultraschic Flow Measurement of the Auxiliary Feedwater Fumps and the Centrifugal Charging Pumps.

2. Pesidual Heat Pemoval (PhR) Suction from Reactor Coolant System (RCS)

FCV-74-1 and -2,

3. Auxiliary Feedwater (AFW) Fump Common Return'to Condensate Storege Tank (CST) - Check Valves 3-894 and 3-895.

4. Essential Faw Cooling Peter (ERCW) Screen Wash Pumps.

5. Reactor Vessel Head Vent Block Velves FSV-68-394 anc -395.

Based on our review of the attached TER, the staff cencludes that the licer.see's requests for relief from certain specific requirements of Section XI of the ASME Code are acceptable. The procesed alternatives will previde an acceptable level of quality and safety. The licensee is required to comply with the IST program defined above in accordance with the relief granted as discussed in the enclosed TER. This SE completes the staff's review of the Sequcyah Units 1 coo 2 IST program.

3.0 CONCLUSION

Basec on the considerations oiscussed above, the staff concludes (1) that relief may be granted pursutnt to paragraph 10 CFR 50.55a(g)(C)(1) based on our findino that certain requirements of Section XI of tre ASPE Boiler and Pressure Vessel Code are irpractical, and (2) tFat granting relief where the

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i i l Code requirements are impractical is authorized by law and will nnt endanger l life er property, or the cotu n defense and security and is otherwise in the -

public interest considering the burden that could result if they were imposed .

on the tacility. l Principal Contributcr: J. Lombardo I 3

Dated: January 19, 1938 ,

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