ML20198N387

Forwards Further Clarification on COP Sys Isolation Valves, in Response to NRC 860417 Request for Addl Info Re TMI Item II.E.4.2(6).Resolution of Item Should Be Reflected in Next Sser

ML20198N387
Person / Time
Site:	Seabrook
Issue date:	06/04/1986
From:	George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To:	Noonan V Office of Nuclear Reactor Regulation
References
TASK-2.E.4.2, TASK-TM SBN-1087, NUDOCS 8606060076
Download: ML20198N387 (8)

Text

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George S. Thomas Vice Fresidert Nuclear Production June 4, 1986 SBN-1087 New Hampshire Yankee Division 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) USNRC Letter, dated April 7, 1986, "Requast for Additional Information from Seabrook Regarding TMI Item II.E.4.2(6)", V. Nerses to R. J. Harrison (c) PSNH Letter (SBN-1049), dated May 13, 1986, " Request for Additional Information; C0P System Isolation Valves", J. D2Vincentis to V. S. Noonan

Subject:

Request for Additional Information; CDP System Isolation i

Valves - Further Clarifications

Dear Sir:

Enclosed please find our further clarification to information re-quested in Reference (b) regarding the C0P System Isolation Valves.

We believe the enclosed and Reference (c) addresses the Staf f's concerns regarding the C0P valves, and request that the resolution of the issue be reflected in the next supplement to Seabrook's SER.

Very truly yours, Y&

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Geo e S. Thomas Enclosures cc: Atomic Safety and Licensing Board Service List 8606060076 860604 PDR ADOCK 05000443 A

PDR

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P.O. Box 300 Seabrook, NH O3874. TeW (603)474-9521

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Dicn3 Curran, Esquire Calvin A. Cann::g Harmon & Weier City Manager 2001 S. Street, N.W.

City Mall Suite 430 126 Daniel Street Washington, D.C.

20009 Portsmouth, NH 03801 i

Sherwin E. Turk, Esq.

Stephen E. Merrill, Esquire

Office of the Executive Lessi Director Attorney General f

U.S. Nuclear Regulatory Commission George Dana Sisbee, Esquire Tenth Floor Assistant Attorney General Washington, DC 20555 Office of the Attorney General 25 Capitol Street Robert A. Beckus, Esquire Concord, MN 03301-4397 114 Lowell Street P.O. Box 516 Mr. J. P. Wadeau Nanchester, NH 03105 Selectmen's Office 10 Central Road Philip Ahrens. Esquire Rye, NH 03870 i

Assistant Attorney General Department of The Attorney General Mr. Angle Nachiros Statehouse Station M Chairdian of the Board of Selectmen hugusta. Nd 04333 Town of Newbury Newbury, MA 01950 Mrs. Sandra Cavutis Chairman, Soard of Selectmen Mr. William S. Lord RF0 1 - Sou 1154 Board of Selectzee Rennsington, NN 03827 Town Na1.1 - Friend Street Amesbury, MA 01913 Carol S. Sneider Esquire Assistant Attorney General Senator Gordon J. Humphrey Department of the Attorney General 1 Pillsbury Street j

One Ashburton Place, 19th Floor Concord, NN 03301 Boston, MA 02104 (ATTN: Herb Boynton)

I Senator Gordon J. Humphrey N. Joseph Flynn Esquire j

U.S. Senate Office of General Counsel Washington, DC 20510 Federal Energency Management Agencyg (ATTN: Tom Burack) 500 C Street, mi Washington, DC 20472 Richard A. Nampe, Esq.

Nampe and McNicholas Paul McEachern, Esquire 35 Pleasant Street Matthew T. Brock, Esquire Concord, NN 03301 Shatnes & NcEachern 25 Naplewood Avenue Donald E. Chick P.O. Box 360 Town Manager Portsmouth, NN 03801 Town of Exeter le Front Street Cary W. Holmes. Esq.

Exeter NM 03833 Holmes & Ells

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47 Winnacunnet Road i

Brentwood Board of Selectmen Hampton, NH 03841 RFD Delton Road I

Brentwood, NH 03833 Mr. 34 Thomas FEMA Region I Peter J. Nathews, Mayor 442 John W. McCormack PO & Courthouse l

City Hall Boston, MA 02109 Newburyport NA 01950 Stanley W. Enowles, Chal:3an Board of Selectmen P.O. Box 710 North Hampton, NH 03862 I- _, - _ _ - -.. _. -

ENCLOSURE TO SBN-1087 C0P VALVE TEST References 1.

PSNH Letter (SBN-1049), dated May 13, 1986, " Request for Additional Information, COP System Isolation Valves", J. DeVincentis to V. S.

Noonan 2.

UE6C Mechanical Nuclear Calculation Set No. 4.3.22-F10, Rev. 1 FSAR Containment Analysis - LOCA 3.

UE&C Mechanical Nuclear Calculation Set No. 4.3.22-F10, Rev. 2 FSAR Containment Analysis - LOCA Question and Responses:

A.

The following replaces the question and response for Question 1.e of Reference (1).

Question Describe the technical basis for using 17 psig as the containment pressure due to a LOCA event (page 17 of Reference 3).

If appropriate, submit a copy of UE6C Change Order 23 dated October 18, 1982 (Document (e) of Reference 3).

Response

For the initial scoping of the test pressure for the C0P valve test, the design envelope curve from FSAR Figure 3.ll(B)-1 (Sht. 1) was used. A time period of two seconds was used.

The corresponding pressure is 17 psig. Then a fit to the actual calculated LOCA responses was done.

The values used were taken from Reference 2.

Table (1) lists the pressure valves for the first eight seconds for the DEPS* with maximum Safety Injection (SI) and the DEllL* for eight oeconds.

The closure signal was assumed to be generated at a con-tainment pressure of 7.4 psig (5 psig setpoint plus 2.4 psig tolerance).

This value has changed since COP valve testing to 4.3 + 1.5 psig tolerance.

A delay of 0.6 seconds was assumed for signal actuation and processing, and closure time of 2.0 seconds was assumed for the valves.

This resulted in a nominsi containment pressure of 16.25 psig. An additional 1/2 second margin was allowed, for further conservativeness, so the pressure value becomes 17.6 psig, see Figure 1.

The containment analysis has been reanalyzed due to an increase in the Refuelfug Water Storaga Tank temperature. The new values were taken from Reference (3). Table (2) lists the pressure values for the first eight seconds for the DEPS and DEHL. Using the same assumptions for Case 1 the pressure value conservatively becomes 18.8 psig, see Figure 2.

ENCLOSURE TO SBN-1087 CDP VALVE TEST (Continued)

Actual testing of the valves was completed using 20 psig minimum for static testing prior to and af ter flow testing.

For flow testing of each valve, pressure at each valve ranged from 17 psig for one case to 23 psig with average number of test cases of 19 psig.

For flow testing of both valves simultaneously, pressure ranges from 17 psig for one case up to 29 psig with an average number of test cases of 24 psig.

A copy of UE&C Change Order 23, dated October 18, 1982 was sub-mitted in Reference (1).

• DEPS - Double End Rupture - Pump Suction DEHL - Double Ended Rupture - Hot Leg B.

Question Provide the document references for C0P valves, 10CFR50 Appendix J.

Type C leak testing.

Response

The C0P valves were Type C tested in acccrdance with Test Procedure PT-37.1 (between March 15, 1986 and March 28, 1986). The NRC (Region I) inspection report associated with the containment inte-grated leak rite test is Inspection Report No. 50-443/85-15.

i _..

ENCLOSURE TO SSN-1087 CDP 7ALVE TEST (Continued)

TABLE 1 - CONTAINMENT PRES $URE TIME (SECONDS)

PRESSURE (PSIG)

I DEPS DEHL 0

.5

.5 1

5.27 4.97 2

9.64 8.93 3

13.29 12.36 l

4 16.09 15.37 5

18.41 18.06 6

20.56 20.61 7

22.56 22.36 8

24.40 25.07 l

EE4 CLOSURE TO SBN-1087 COP VALVE TEST--~

(Continued)

TABLE 2 - CONTAINMENT PRESSURE TIME (SECONDS)

PRESSURE (PSIG) l DEPS DEHL 0

1.5 1.5 1

6.15 5.79 2

10.65 9.85 3

14.36 13.32 4

17,18 16.32 5

19.52 19.0 5 6

21.68 21.61 7

23.7 23.89 8

25.56 26.09

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