ML20204A379

Forwards Setpoint Info & Revised Excerpt from FSAR Section 1.9 Documenting Compliance to NUREG-0737,Items II.K.3.1 & II.K.3.2.Hardware Info Provided in 860317 Submittal Re NUREG-0737,Task II.D.1

ML20204A379
Person / Time
Site:	Seabrook
Issue date:	05/07/1986
From:	Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Noonan V Office of Nuclear Reactor Regulation
References
RTR-NUREG-0694, RTR-NUREG-0737, RTR-NUREG-694, RTR-NUREG-737, TASK-2.D.1, TASK-2.K.3.01, TASK-2.K.3.02, TASK-TM SBN-1038, NUDOCS 8605120142
Download: ML20204A379 (5)

Text

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• SEABROOK STATION Engineering Office d) ( """ (

-) I May 7, 1986 SBN- 1038 l Putsc Service of New Hampshire T.F. B7.1.2  !

United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5

References:

(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) WCAP-9804, "Probabilistic Analysis and Operational Data in Response to NUREG-0737, Item II.K.3.2, for Westinghouse NSSS Plants", dated February 1981 (Nonproprietary).

(c) SBN-969, "NUREG-0737, Task II.D.1, ' Perf o rmance Testing of Boiling Water Reactor and Pressurized Water Reactor Relief and Safety Valves'," dated March 17, 1986.

Subj ect : TMI Task Items II.K.3.1 and II.K.3.2; Request for Additional Information

Dear Sir:

In recent discuaatona with the Staff wa were requented to provide additional information regarding our response to Task Items II.K.3.1 and II.K.3.2. The following is provided in response to the Staf f's request.

In WCAP-9804 Westinghouse states that "the analysis has included sensitivity studies to accommodate dif ferences among plants including FORV block probability, safety injection system design, and operator reliability, rendering the probabilistic analysis generically applicable to all Westinghouse NSSS plants". Westinghouse also states that the data (used in the analysis) "for Westinghouse operating plants for pre-and post-TMI operation show a strong correlation with the results of the probabilistic analysis".

We have reviewed in detail all of the plant input assumptions to the W probabilistic analysis (Section 3.4 of WCAP-9804). Based on our review, we have found nothing unique to Seabrook that is unconservative with respect to the input assumptions used in the Westinghouse analysis.

The information requested regarding the hardware (e.g. , model, type, manufacturer) is provided in Reference (c). The information concerning setpoints is provided in Attachment 1.

8605120142 43 ADOCK g 8 h PDR c0 PDR i l Seabrook Station Construction Field Office . P.O. Box 700 . Seabrook. NH 03874

1

's United States Nuclear Regulatory Commission Attention: Mr. Vincent S. Noonan Page 2 We have also included as Attachment 2 a revised excerpt of FSAR Section 1.9 documenting our compliance with the above referenced TMI Task Items. This revised excerpt will be incorporated into the FSAR by a future amendment.

We trust the enclosed information is acceptable and request that this be reflected in the next supplement to Seabrook's SER.

Very truly yours, John DeVincentis Director of Engineering Attachments cc: Atomic Safety and Licensing Board Service List J

i

Diane Curren. Esquire Calvio A. Canneg' N;rson & Weiss City Managir 2001 8. Street, N.W. ( ity Mall -

Suite 430 126 Daniel Street Washington, D.C. 20009 -

Portsmouth, MN 03801 Sherwin E. Turk, Esq. Stephen E. Merrill, Esquire i Office of the Executive Legal Director Attorney General 3:

U.S. Buclear Regulatory Commission George Dana 81sbee, E, squire l!

Tenth Floor Assistant Attorney General ?l Washington, DC 20555 office of the Attorney General II 25 Capitol Street Robert A. Backus, Esquire Concord , W 03301-4397 116 Lowell Street P.O. Box 516 Mr. J. P. Nadeau Manchester EN 03105 Selectmen's Office 10 Central Road Philip Ahrens. Esquire Rye, EH 03870 Assistant Attorney General Department of The Attorney General Mr. Angle Nachiros Statehouse Station M Chairman of the Board of Selectmen hugusta MB 04333 Town of Newbury Newbury, MA 01950 Mrs. Sandra Cavutis Chairman, Boar 11 of Selectmen Mr. William S. Lord RFD 1 - Box 1154 Board of Selectmen Kennsington, EN 03427 Town Nall - Friend Street Amesbury, MA 01913 Carol S. Sneider Esquire Assistant Attorney General Senator Cordon J. Humphrey Department of the Attorney General 1 Pillsbury Street One Ashburton Place, 19th Floor Concord, W 03301 i

Boston, MA 02108 (ATTN: Herb Boynton)

Senator Cordon J. Numphrey N. Joseph Flynn, Esquire U.S. Senate Office of General Counsel ,

Washington, DC 20510 Federal Meersency Management Agency g (ATTW: Tom Burack) 500 C Street, SW ' ,

Washington, DC 20472 i j Richard A. Hampe, Esq.

i Hampe and McElcholas Paul McEachern, Esquire 35 Pleasant Street Matthew T. Brock, Esquire Concord, NH 03301 Shatnes & NcEachern 25 Naplewood Avenue Donald I. Chick F.C. Box 360 Town Manager Portsmouth, NH 03801

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Town of Exeter 10 Front Street Cary W. Holmes, Esq.

Exeter, W 03833 Holmes & Ells 47 Winnacunnet Road Brentwood Board of Selectmen Hampton, NH 03841 RFD Dalton Road Brentwood, NH 03833 Nr. Ed Thomas FEMA Region I Peter J. Nethews, Mayor 442 John W. McCormack PO & Courthouse City Hall Boston, NA 02109 Newburyport, MA 01950 Stanley W. Inowles, Chairman Board of Selectmen P.O. Box 710 North Hampton. NH 03862

9 SBN- 1038 ATTACHMENT I DESCRIPTION SETPOINT Reactor Trip on High Pressurizer 2,385 psig Pressure Pressurizer Pressure Control - Pref 2,235 psig Power Relief Valve (PCV-456A) Operated 150 psi on Pressure Deviation Signal Power Relief Valve (PCV-456B) Operated 2,335 psig on Actual Pressure Power Relief Valve Interlock 2,335 psig (PCV-456A, PCV-456B)

Power Relief Valve Isolation valve 2,350 psig (Block Valves) Opening Activation (Normally Open)

P-9 (Automatically Blocks 20% of Full Reactor Trip on Turbine Trip Power Below Setpoint Power Level)

Pressurizer Code Safety Valves 2,485 psig

' A%%ed8 sex-Iosa SB 1 & 2 Amsndesnt 56 FSAR November 1985

Response

i Westinghouse, as part of the response prepared for the Westinghouse Owners Group to address Item II.K.3.2, has evaluated the necessity of incorporating an automatic pressurizer power operated relief valve isolation system. This evaluation is documented in Reference 2 and concluded that such a system should not be required.

> IAMEET 'M "

Task II.K.3.2 Report on Overall Safety Effect of Power Operated Relief Valve Isolation System (NUREG-0737)

Position:

(1) The licensee should submit a report for staff review documenting the various actions taken to decrease the probability of a small break Loss-of-Coolant Accident (LOCA) caused by a stuck-open Power-Operated Relief Valve (PORV) and show how those actions constitute sufficient improvements in reactor safety.

(2) Safety valve failure rates based on past history of the operating plants designed by the specific Nuclear Stream Supply System (NSSS) vendor should be included in the report submitted in response to (1) above.

Response

As mentioned in the response to item II.K.3.1, the Westinghouse Owners Group has submitted a Westinghouse prepared report (Reference 2) which provides a probabilistic analysis to determine the probability of a PORV LOCA, estimates the effect on the post TMI modifications, evaluates an automatic PORV isolation concept, and provides PORV and safety valve operational data for Westinghouse plants. Because of the sensitivity analyses included in the report, the report is generic and is applicable to the Seabrook Station.

The report identifies a significant reduction in the PORV LOCA probability as a result of post TMI modifications, and the calculations compare favorably with the operational data for Westinghouse plants (included as an appendix to the report).

> INSER T "A" Task II.K.3.3 Reporting SV and PORV Challenges and Failures (NUREG-0694)

Position:

Assure that any failure of a PORV or safety valve to close will be reported to the NRC promptly. All challenges to the PORVs or safety valves should be documented in the annual report.

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