ML20154H307

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Safety Evaluation Accepting Licensee Requests for Relief from Certain Specific Requirements of ASME Code,Section XI
ML20154H307
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 09/15/1988
From:
NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20154H289 List:
References
NUDOCS 8809210251
Download: ML20154H307 (2)


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EMCLOSURE SAFETY EVALUATION REPORT BY THE OFFICE OF SPECIAL PROJECTS PUMP AND VALVE INSERVICE TESTING PROGRAM i

TENNESSEE VALLEY AUTHORITY l

SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328

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1.0 !NTRODUCTION j

i Section 50.55a, "Codes and Standards," of 10 CFR Part 50 requires, in part, that l

1 certain safety-related pumps and valves meet the requirements of Section XI of i

the American Society of Mechanical Engineers (ASME) Boiler and Pressure Yessel I

Code (hereafter "the C,Je").

In order to meet the requirements of this regulation, the Tennessee Valley Authority (TVA) has submitted to the NRC its first ten-year f

Inservice Testing (IST) program on pumps and valves for the Sequoyah Nuclear Plant, Units 1 and 2.

The staff issued Safety Evaluation Reporte (SERs) concerning the Sequoyah IST program on April 5, 1985, October 23, 1987, t

i January 19, 1988 March 14, 1980 (Unit 2 only), and August 18, 1988 (Unit 1 only).

This SER addresses three relief requests made in TVA submittals dated

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l April 22 and August 4, 1988.

Requests 1 and 2 in the letters have been identified r

by TVA as needing resolution prior to Unit I restart, j

Regulation 10 CFR 50.55a(g)(6)(1) authorizes the Comission to grant relief from these Section XI requirements upon making the necessary findings. This SER contains the NRC staff's findings with respect to granting or not granting reliefs submitted as part of TVA's IST program.

2.0 EVALUATION l

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l By letter dated January 19, 1988, the staff granted requests for relief from l

instrument accuracy requirements of IWP-4110 for flow reasurements of the b

auxiliary feedwater and centrifugal charging purps. This present SER addresses i

safety injection (SI), contairrent j

similar relief requests on the following(pumps:ERCW), component ecoling water (CCW), j spray (CS), essential raw cooling water residual heat removal (RHR), and the diesel fuel oil transfer (DFOT).

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i addition, TVA has requested relief from the requirerents of !WV-3411 for the nerformance of the ERCW valves quarterly stroke test requirements.

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The NRC contractor. Oak Ridge National Laboratory, has reviewed the licensee's three relief recuests and prepared the attached Technic >' Evaluation Report i

(TER). The staff Fas reviewed the TER and concurs in i'

?ases and findings, r

j The granting of relief is based upon the fulfillment of corraitments made i

by TVA in its basis for each relief request and the alternate proposed i

testing.

8809210251 080915 PDR ADOCK 05000327 P

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2 For all the pumps, TVA committed to an accuracy of 3% acceptance criteria for ultrasonic flow measurements.

For the ERCW, CCW, RPR and DFOT pumps TVA has also nsde the following comnitments.

TVA stated that (1)'it will use ultrasonics as a backup flow measurenent for the pumps in lieu of plant. installed flow instrumentation only when problems are encountered with the plant instrumer.;ation and (2) maintenance and calibration of the plant installed flow instrumentation will be conducted in a timely manner to For the ERCW valves TVA committed to preclude repeated use of ultrasonics.

full stroke exercise these valves at least once each refueling outage or each l

time the ERCW heat exchanger chemistry requires cleanup and layup but at a frequency not to exceed once per quarter.

Relief has been granted from tha testing requirements which the staff has determined to be impractical to perform, wculd not compromise the safety of the plant, and where testing,1f implemented, would result in undue hardship, and by determination that the relief requests were evaluated in accordance with 10 CFR 50.55a(g)(6)(i).

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3.0 CONCLUSION

Based on the staff review of the attached TER, regarding three relief requests for the Sequoyah Nuclear Plant. Units 1 and 2 the staff concludes that TVA9 requests for relief from certain specific requirenents of Section XI of the The licensee is required to comply with the IST ASME Code are acceptable.

program defined above in accordance with the relief granted in the enclosed

TER, Review of the overall IST program has been completed.

Any additional program changes such as revisions or additional relief requests or deletion of any comoonents from the IST program should be submitted for staff review and

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should not be implemented prior to review and aoproval by the staff.

The staff has determined that pursuant to 10 CFR 50.55afg)(6Hi) granting relief 1

where the Code requirements are irpractical is authorized by law and will not i

i The staff has endanger life or property, or the common defense and security.

also concluded that granting relief is otherwise in the public interest considering the burden that could result if the requirements were irposed on the facility.

Principal Contributor:

J. Lombardo f

Dated: September 15, 1933 l

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