ML20128E523

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Forwards Public Notice Announcement of Application for Amend to License DPR-44.Amend Would Modify TS 3.6.D.2 Requirements for safety-relief Valve Operability
ML20128E523
Person / Time
Site: Peach Bottom Constellation icon.png
Issue date: 02/04/1993
From: James Shea
Office of Nuclear Reactor Regulation
To: Beck G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
TAC-M85685, NUDOCS 9302100494
Download: ML20128E523 (5)


Text

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February 4, 1993 Docket No. 50-277

, Mr. George J. Beck Manager-Licensing,.MC 52A-5.

Piilladelphia Electric Company Nuclear Group Headquarters Correspondence Control Desk P.O. Box No. 195 Wayne, Pennsylvania 19087-0195

Dear Mr. Beck:

SUBJECT:

PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO OPERATING LICENSE FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT 2 (TAC M85685)

The enclosed announcement has been forwarded to the Lancaster New Era, Lancaster Intelligencer Journal, York Daily Record, York Dispatch and Bel Air, Maryland, Aegis for aublication. This announcement relates to your application dated Fearuary 2, 1993, for an amendment to Facility Operating License No. DPR-44, to modify the Technical Specification 3.6,0.2 requirements for safety-relief valve operability.

A separate notice will be published.later in the Federal Reaister concerning the revision to the SRV TS requirements, Sincerely, l

/S/

Joseph W. Shea, Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Announcement

' cc w/ enclosure:

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%g, February 4, 1993 DocketNo. 50-277' Mr. George J. Beck .

Manager-Licensing, MC 52A-5 Philadelphia Electric Company ,

Nuclear Group Headquarters Correspondence Control Desk P.O. Box No. 195 Wayne, Pennsylvania 19087-0195-

Dear Mr. Beck:

SUBJECT:

PUBLIC NOTICE OF APPLICATION FOR AMENDHENT TO OPERATING LICENSE FOR PEACH BOTTOM ATOMIC POWER STATION,: UNIT 2 (TAC M85685)

The enclosed announcement has been forwarded to the Lancaster New Era,-

Lancaster Intelligencer Journal, York-Daily Record,:. York Dispatch and Bel- Air,;

Maryland, Aegis for aublication. This announcement relates to your:

- application dated Fe3ruary-2, 1993,-for an amendment to Facility Operating License No. DPR-44, to modify the Technical Specification 3.6,0.2 requirements for safety-relief valve operability.

A separate notice will be published later in the Federal Reoister concerning; the revision.to the SRV TS requirements.

Since ly, 0 V -

J stp W. Shea, Project Manager-Project" Directorate:I-2.

Division of Reactor Projects? I/II-Office of Nuclear Reactor Regulation

Enclosure:

Announcement m-cc w/ enclosure:

See next page-4 e * * -me <a --_--------_.--l.---

'.l

-Mr. George J. Beck Peach Bottom Atomic Power Station, Philadelphia Electric Company Units 2 and 3 CC:

J. W. Durham, Sr., Esquire Mr. Thomas M. Gerusky, Director' Sr. V.P. A General Counsel Bureau of Radiation-Protection-Philadelphia Electric Company Pennsylvania Department of 2301 Market Street, S26-1 Environmental Resources Philadelphia, Pennsylvania 19101 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Philadelphia Electric Company ATTN: Mr. D. B. Miller, Vice President Board of- Supervisors Peach Bottom Atomic Power Station Feach. Bottom Township Route 1, Box 208 R. D. #1 Delta, Pennsylvania 17314 Delta, Pennsylvania 17314 Public Service Commission of Philadelphia Electric Company Maryland ATTN: Regulatory Engineer, Al-2S Engineering Division Peach Bottom Atomic Power Station ATTN: Chief Engineer Route 1, Box 208 231 E. Baltimore Street Delta, Pennsylvania '17314 Baltimore,' MD 21202-3486 Residt 'nspector Mr. Richard McLean U.S. h, aar Regulatory Commission Power-Plant and Environmental Peach Bottom Atomic Power Station Review Division P.O. Box 399 . Department of Natural Resource's-Delta, Pennsylvania 17314 B-3, Tawes States Office Building Annapolis, Maryland 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road .

King of Prussia, Pennsylvania 19406 Mr. Roland Fletcher Department of Environment 201 West Preston Street Baltimore, Maryland 21201 l Carl D. -Schaefer

. External Operations - Nuclear

!' Delmarva Power & Light Company P.O. Box.231 Wilmington, DE 19899 l

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  • i PUBLIC NOTICE I

NRC STAFF CONSIDERING LICENSE AMENDMENT REQUEST FOR PEACH BOTTOM, UNIT 2 The Nuclear Regulatory Commission (NRC) has received an application dated February 2,1993 from Philadelphia Electric Company (the licensee) for an exigent amendment to Appendix A of the operating license for Peach Bottom Atomic Power Station, Unit 2, located in York County, Pennsylvania, if approved, the amendment would add a footnote to Technical Specification (TS) Section 3.6.D.2, allowing continued operation with one safety / relief valve (SRV) inoperable until the next outage of sufficient duration which requires a drywell entry to allow entry into the drywell to fix the valve without undue risk to plant personnel. The valve is considered inoperable due to a bellows failure which affects the mechanical pressure setpoint of the valve; the automatic and manual depressurization function of the valve, part of the Automatic Depressurization System (ADS), will remain operable. The licensee has performed bounding analyses that conclude that operation in this configuration is acceptable. The plant has 11 safety / relief valves, 5 of which have the ADS function, and 2 safety valves to provide overpressure protection for the reactor coolant piping. This amendment would be in effect on a one-time only basis until the valve is repaired.

The NRC has determined that the licensee used its best efforts to'make a timely application for the proposed change and that exigent circumstances do exist and were not the result of any fault of the licensee. The exigent circumstances result from the fact that the current operating license contains a limiting condition for operation (LCO) of 30 days following the determination of inoperability of a safety / relief valve. The licensee entered this LC0 on January 18, 1993, when the bellows failure alarm originally came in. The need for this TS change was not determined until approximately January 26, 1993, after assessment of the circumstances of the alarm.

Consequently, the NRC has determined that these exigent circumstances justify reducing the public notice period normally provided for licensing amendments and proposes to issue the amendment at the close of business February 12, 1993.

The licensee has evaluated the requested amendment against the standards in 10 CFR 50.92 and the NRC staff has made a proposed (preliminary) determination that the requested amendment involves no significant hazards considerations. Under NRC regulations, this means that the proposed amendment does not involve a significant in:rease in the probability or consequences of an accident, would not create the possibility of a new or different kind of accident, or involve a significant reduction in a safety margin. The licensee's analysis is presented below:

1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed TS change involves a change in the allowable out of service time of an SRV. SRV's are not an initiator for any of the over pressurization transients that the SRVs are designed to help l

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2-I mitigate. A stuck open relief valve is an accident _ initiator; ,

however, the condition which has caused the SRV to be inoperable does I not increase the probability of a stuck open relief valve. The .

design of the valve is such that a failed bellows will equalize the pressure across the first stage pilot piston and thus prevent the piston from moving and the valve from opening.

The analysis provided in the safety discussion clearly shows that the consequences of any of the overpressurization transients do not increase with the SRV inoperable. Further, while the probability of a stuck open relief valve remains unchanged by this condition, the stuck open relief valve transient was analyzed and the station can fully handle this event.

2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed TS change involves a change in the allowable out of- I service time for an SRV. The proposed change does not introduce any new accident initiators since there are no physical changes being l made to the facility. 1

3. The proposed change does not involve a significant reduction in a margin of safety.

The Technical Specification Bases define two design bases for the pressure relief system; first, to meet ASME overpressurization criteria, and second, to prevent opening of the unpiped spring safety valves during normal plant isolation and load rejections. First,_

analysis has shown that ASME overpressurization criteria will be met.

Second, this same analysis has shown that an unpiped-spring safety valve may potentially lift if two SRVs are inoperable. However, the analysis assumptions associated with the ASME overpressurization criteria are much more conservative than the analysis assumptions required for demonstration that.unpiped spring safety _ valves _are not opened during normal plant isolations or load rejections. Analysis of the HSIV closure overpressure event with a functional MSIV .

position switch scram signal and two inoperable SRVs yields a peak steam line pressure below the unpiped spring safety valve setpoint.

If the proposed determination that the requested license amendment involves no significant hazards consideration becomes final, the NRC will issue the amendment without first offering an opportunity for a public hearing. An opportunity for a hearing will be published in the Federal Reaister at a later date and any hearing request will not delay the effectivo date of the amendment.

If the NRC staff decides in its final determination that the amendment does involve a significant hazards consideration, a notice of opportunity for a prior hearing will be published in the Federal Reoister and, if a hearing is granted, it will be held before the amendment is issued.

r l

Comments on the proposed determination of no significant hazards consideration may be telephoned to Charles Hiller, Director, Project Directorate I-2, by collect call to 1-(301) 504-1430, or submitted in writing to the Rules and Directives Review Branch, Division of Freedom of Information and Publication Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555. All comments received by close of business on February 12, 1993, will be considered in reaching a final determination. A copy of the application may be examined at the NRC's Local Public Document Room located at the Government Publications Section, State Library of Pennsylvania, (REGIONAL DEPOSITORY) Education Building, Walnut Street and Commonwealth Avenue, Box 1601, Harrisburg, Pennsylvania 17105, and at the Commission's Public Document Room, the Gelman Building, 2120 L Street, N.W., Washington, DC 20555.

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