ML19350C741

RO 81-029:on 810312,discrepancy Noted Between Plant Mod Manual & Tech Specs During Review of Inservice Insp Requirements for Mods Recently Completed on 0.75 & 1-inch Branch Connection on RCS & Safety Injection Sys

ML19350C741
Person / Time
Site:	Beaver Valley
Issue date:	03/26/1981
From:	Werling J DUQUESNE LIGHT CO.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
BVPS:JAW:1134, RO-81-029, RO-81-29, NUDOCS 8104060650
Download: ML19350C741 (4)

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' 5" DUQUESNE LIGHT COMPANY Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077

- March 26, 1981 BVPS: JAW:1134 Beaver Valley Power Station, Unit No. 1 , 4 Docket No. 50-334. License No. DPR-66 g y,-c

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Mr. B. H. Grier, Director of Regulation ~

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United States Nuclear Regulatory Commission I 2 % 3n> ,. "9 7 b Gf 8 Region 1 (1,\ CMISD7"cos/Q' 631 Park Avenue yN /

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Dear'Mr. Grier:

In accordance ylth Appendix A, Beaver Valley Technical Specifications,

, Licensee Event Report LER 81-29/0lP, Technical Specification 4.0.5, Inservice Inspection Program, is submitted. This occurrence was reported to the Beaver Valley Resident Inspector, Mr. D. A. Backman, at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on March 25, 1981.

Da March 12,,1981, the Duquesne Light Company Nuclear Services Quality Control (USQC), while performing a review of the Inservice Inspection (ISI) requirements for modifications recently completed on a 3/4" and 1" branch connection on the Reactor Coolant System and Safety Injection System, respectively, noted a discrepancy between the Plant Modification Manual (P)D1) and the Technical

Specifications. The hydrostatic test requirement.s of the P)DI referenced the 1977 edition through the 1978 summer' addenda of ASME XI, while the Technical Specifications require hydrostatic testing be performed to the 1974 edition through the 1975 summer addenda of ASME XI. NSQC requested that DLCo Engineering evaluate the noted discrepancy.

Duquesne light Company Engineering informed the station that the application-ef the ":Di restitcd in the folloaing two differences between the two editions of-the Code.

1) Branch connections 1" or less are exempted f rom hydrostatic testing

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after repair'or modification. These lines are not exempted from i hydrestatic testing-under the edition of the' code required by the Technical Specitications.

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'Mr. B. II. Grier March 26, 1981 BVPS: JAW:1134 Page 2

2) A hydrostatic test time of ten (10) minutes for exposed areas was permissible under the Code subsection lWA-5210 referenced in the PMM.

A test time of four (4) hours for all areas exposed or unexposed, is required under the subsection of the Code endorsed by the Technical Specifications.

Item (1) was' applied to the hydrostatic testing requirements of the two branch connection e.odifications performed during the current plant shutdown.

Item (2) was applied to the modifications completed during the, refueling and modification outage from December 1, 1979 through November 22, 1980.

The discrepancy resulted when the MM was prepared and the requirements of 10 CFR 50.55a(g)(4)(1) were misinterpreted. The use of the two applications is technically justified in that: Item (1) was presented as Code Case N-210 and was approved by the ASME Council on March 20, 1978 and was subsequently incorporated in the 1978l summer addenda of the 1977 edition of ASME XI. Code Case N-210 was also, endorsed in Regulatory Guide 1.147 issued by the NRC in February, 1981.

-Item (2) was incorporated in the 1975 winter addenda of the 1974 edition of ASME XI Land subsequently in the 1977 edition of ASME XI. The 1977 edition through the 1978

summer addenda of ASME XI has been endorsed by 10 CFR 50.55a(b) . There are no potential safety effects resulting from the use of the two applications.

Originally, relief was granted from Subsection IWA-5210 paragraph (a) via the 'teacter Coolant Systc= Technical Specification bases, which stated: " Repairs en' components 2 inches in diameter or smaller receive a surface examination which

. assures a similar, standard of integrity" and "...a leak test will ensure leak tightness during normal. operation".

The failure to obtain an exemption from Subsection IWA-5210 paragraph (a)

-and permission to invoke Code Case N-210 prior to applying their specific use

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in. the Beaver Valley: Power Station ISI program is a violation of Technical Specif,1 cation 4.05, Limiting Condition for Operation related to Inservice Inspection.

Very truly yours,

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J. A. Werling Superintendent s~ ' . . ' '- % _

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Mr. B. H. Grier

March 26, 1981 BVPS

JAW:1134

.Page 3 cc: _ - Director Of Management & Program Analysis United States Nuclear Regulatory Commission Washington,-D. C. 20555 Director, Office of Inspection and. Enforcement Headquarters

~ United States Nuclear Regulatory Commission Washington, D. C. - 20555 2

D. A. Chaney, BVPS Licensing Project !!anager United States Nuclear Regulatory Commission Washington, D. C. 20555 D. A. Beckman, Nuclear Regulatory Commission, BVPS Site Inspector Nuclear Safety Analysis Center, Palo Alto, California G. E. Muckle, Factory Mutual Engineering, Pittsburgh d .Mr.! John' Alford, PA Public Utilities Commission, Harrisburg, PA i

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