ML20058F363

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Grants Requests for Relief from Section XI of ASME Code Re Inservice Testing of Pumps & Valves.Encl Safety Evaluation Lists Requests for Relief Granted & Denied & Pumps & Valves Requiring Alternate Testing
ML20058F363
Person / Time
Site: Beaver Valley
Issue date: 06/29/1982
From: Varga S
Office of Nuclear Reactor Regulation
To: Carey J
DUQUESNE LIGHT CO.
Shared Package
ML20058F368 List:
References
TAC-11260, TAC-11261, TAC-6363, NUDOCS 8207300455
Download: ML20058F363 (6)


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DEisenhut 0 ELD Docket No. 50-334 AE0D IE ACRS-10 WRoss Mr. J. J. Carey, Vice President CParrish Duquesne Light Company RCilimberg Nuclear Division RJBosnak Post Office Box 4 JPKnight Shippingport, Pennsylvania 15077 Gray File

Dear Mr. Carey:

By letter dated May 2,1979, as revised March 17, 1980, you submitted a proposed inservice testing program description and request for relief from testing requirements pursuant to 10 CFR 50.55a(g). The purpose of this letter is to inform you of the results of the staff review of your relief requests and to grant relief in part from the requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (the Code) or impose other requirements, as appropriate.

The review of requests for relief from the pump and valve testing requirements of the Code included in your submittal of March 17, 1980 has been ccmpleted.

j Pased on the results of this review, the staff has determined there are cases in which the requests relief cannot be granted, others where alternate testing is necessary, and those where relief can be granted as requested. Additionally, it has been determined that certain pressure isolation valves should have testing conducted in addition to the exercising requirements of the Code.

Your submittal of March 17, 1980 and the EG&G Technical Evaluation Report (attached to SER) address the period January 30, 1980 through September 29, 1 981. The staff's safety evaluation, however, addresses the first ten year inspection interval for your facility and the relief granted and the alternate testing imposed are intended to cover the period October 1,1976 through September 30,19R6.

It is not anticipated that the scope of your requests for relief will change with this expansion of the interval. However, if you determine that additional relief is needed, you should sutnit a supplemental request for relief and provide justification for your request.

Section 50.551(g) of 10 CFR Part 50 requires that your program be revised at 120 nonth intervals with the start of commercial operation being the reference date. The start of the next interval for your facility is October 1,1986, and your inservice inspection and testing program must be based on the edition and addenda of the Code incorporated by 10 CFR 50.55a(b) 12 nonths prior to that date. Any' changes to your Technical Specifications are required to be subnitted at least six months prior to the beginning of a 120 month interval and it is requested that any requests for relief from Code requirements be t

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WRoss t'r. J. J. Carey, Vice, President CParrish Duquesne Light Company RJBosnak fluclear Division JPKnight Post Office Box 4 Gray File Shippingport, Pennsylvania 15077

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Dear Pr. Carey:

.s By letter dated May 2,1979, as revised March 17, 1980, you submitted a proposed inservice testing program description and request for relief from testing requirements pursuant to 10 CFR 50.55a(g). The purpose of this letter is to infom you of the results'of the staff review of your relief requests and to grant relief from the requirements of Section XI of the American Society of Mechanical Engineers Roller and Pressure Vessel Code (the Code) or impose other requirements, as appropriate.

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The review of requests for relief from the p' ump and valve testing requirements i

of the Code included in your submittal of March 17, 1980 has been completed.

Based on the results of this review, the staff has detemined there are cases thers where alternate testing in which the requested relief cannot be granted, (d as requested.

is necessary, and those where relief can be grante Additionally, i

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it has been determined that certain pressure isolation valves'should have testing conducted in addition to the exercising requirements of the Code.

N Your submittal of March 17, 1980 and the EGAG Technical Evaluation Itaporthc4 thr' ugh September 29, (att&ched to SER) address the period January 30, 1980 o

1681. The staff's safety evaluation, however, addresses the first ten year inspection interval for your facility and the relief grantedsand the alternate testing imposed are intended to cover the peitod October 1,1976 through l

September 30, 1986. It is not anticipated that the scope of your requests l

for relief will change with this expansion of the interval. However, if you determine that additional relief is needed, you should sutnit a supplemental request for relief and provide justification for your request.

Section 50.55a(g) of 10 CFR Part 50 requires that your program be revksed at 120 month intervals with the start of commercial operation being the reference date. The start of the next interval for your facility is October 1,1986, j

and your inservice inspection and testing program nust be based on the edi on and addenda of the Code incorporated by 10 CFR 50.55a(b) 12 months prior to that date. Any changes to your Technical Specifications are required to be submitted at least six months prior to the beginning of a 120 nonth interval

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and it is requested that any requests for relief from Code requirements be

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l Mr. J. J. Carey provided on the same schedule. The staff review of your relief requests for your next interval *111 be conducted on a schedule based on the program-revision requirments for your facility and is scheduled to be completed by October 1,1986 Until that time you should follow the inservice testing progran proposed by your letter dated March 17, 1980, modified as described herein and by any further relief granted or additional testing imposed during the remainder of the period. Any relief from Code requirements granted herein expires on October 1,1986.

The enclosed Safety Evaluation (Enclosure 1) delineates those items for which relief has been granted and alternate schedules and procedures defined.

The staff has determined that where stated the Code requirements are impratical, the granting of this relief is authorized by law and will not endanger lin -

or property or the common defense and security, and is otherwise in the public interest condidering the burden that could result if they were imposed on your facility. The staff has further determined that this action does not conflict with or require revision of the Beaver Valley Unit 1 Technical Specifications.

A copy of the related Notice of Granting of Relief is enclosed.

Sincerely, Original signed by1 S. A yarga r '

Steven A. Varga, Chief Operating Reactors Branch #1 Division:of Licensing

Enclosures:

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Safety Evaluation Report i

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Staff Guidance l

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cc w/ enclosures:

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fa k J. J. Carey r provided on the same schedule. The staff review of your relief requests for your next, interval will be conducted on a schedule based on the program revision requirements for your facility and is shHeduled to be completed by October 1, '1986. Until that time you should follow the inservice testing program proposed by your letter dated March 17,198N modified as described herein and by'a_ny further relief granted or additional testing imposed during the remainder ofsthe period. Any relief from Code requirements granted herein expires on October 1,1986.

The enclosed Safety valuation (Enclosure 1) delineates those items for which relief has been granted and alternate schedules and procedures defined.

We have determined that the granting of this relief is authorized by law and s

will not endanger life or property, or the ctrimon defense and security, s

and is otherwise in the public interest.

In making this determination, we have given due consideration to the impracticality of the Code requirements and the burden that could result if they were imposed on your facility.

N A copy of the rolated Notice of Issuance is enclosed.

Sincerely,

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\\Steven A. Varga, Chief Operating Reactors Branch #1 Divi ion of Licensing

Enclosures:

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Safety Evaluation Report 2.

Staff Guidance 3.

Notice of Issuance cc w/ enclosures:

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Mr. J. J. Carey Based on the review summarized herein, the staff concludes that the relief granted and alternate testing imposed through this document give reasonable assurance that the pump and valve operational readiness intended by the Code will be satisfied. Additionally, we have concluded that this relief does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin; and that there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner.

of 10 CFR Part 50 requires that your program be revised at Section 50.55 (g)ls with the start of commercial operation being the reference 120 month interva date. The start' f the next interval for your facility is October 1,1986, and your inservic nspection and testing program must be based on the edition and addenda of the de incorporated by 10 CFR 50.55a(b) 12 months prior to that date. Any changes to your Technical Specifications are required to be submitted at least si months prior to the beginning of a 120 month interval and it is requested t any requests for relief from Code requirements be provided on the same sc dule. The staff review of your relief requests for your next interval will conducted on a schedule based on the program revision requirements for your faci ity and is scheduled to be completed by October 1, 1986.

Until that time you hould follow the inservice testing program proposed by your letter dated March 1 1080, modified as described herein and by any further relief granted or addi onal testing imposed during the remainder of the period. Any relief from Co requirements granted herein expires on October 1,1986.

Sincerely, Stev A. Varga, Chief Operat Reactors Branch #1 Division f Licensing

Enclosures:

1.

Review Summary 2.

Safety Evaluation Report 3.

Staff Guidance cc w/ enclosures:

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Mr. J. J. Carey Duquesne Light Company cc:

Mr. H. P. Williams Mr. J. D. Sieber, Manager Station Superintendent Nuclear Safety and Licensing Duquesne Light Company Duquesne Light Company Beaver Valley Power Station Nuclear Division Post Office Box 4 Post Office Box 4 shippingport, Pennsylvania 15077 Shippingport, Pennsylvania 15077 Mr. T. D. Jones, Manager Resident Inspector Nuclear Operations U. S. Nuclear Regulatory Commission Duquesne Light Company Post Office Box 298 Post Office Box 4 Shippingport, Pennsylvania 15077 Shippingport, Pennsylvania 15077 Ronald C. Haynes B. F. Jones Memorial Library Regional Administrator - Region I U. S. Nuclear Regulatory Commission 663 Franklin Avenue Aliouippa, Pennsylvania 15001 631 Park Avenue King of Prussia, Pennsylvania 19406 Gerald Charnof f, Escuire Jay E. Silberg, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.W.

Washington, D.C.

20036 Karin Carter, Esquire Special Assistant Attorney General Bureau of Administrative Enforcement 5th Floor, Executive House Harrisburg, Pennsylvania 17120 Marvin Fein Utility Counsel City of Pittsburgh 313 City-County Building Pittsburgh, Pennsylvania 15219 Mr. John A. Levin Public Utility Commission P.O. Box 3265 Harrisburg, Pennsylvania 17120 Irwin A. Dopowsky, Esquire Office of Consuner Advocate 1425 Strawberry Square Harrisburg, Pennsylvania 17120 Charles A. Thomas, Esquire Thomas and Thomas 212 Locust Street Box 999 Harrisburg, Pennsylvania

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