ML20199C235

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Responds to Questions Re Sser 4,Section 3.10, Seismic & Dynamic Qualification of Safety-Related Mechanical & Electrical Equipment. Program to Reconcile Generic g-loading of NSSS Valves Will Be Completed by 860630
ML20199C235
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 06/13/1986
From: Devincentis J
PUBLIC SERVICE CO. OF NEW HAMPSHIRE
To: Noonan V
Office of Nuclear Reactor Regulation
References
SBN-1111, NUDOCS 8606180001
Download: ML20199C235 (3)


Text

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6 SEABROOK STATION Enginscring Office June 13, 1986 M W d h We NEW HAMPSHIRE YANKEE DIVISION B7.

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 Subj ect :

Response to Section 3.10 of SSER 4, " Seismic and Dynamic Qualification of Safety-Related Mechanical and Electrical Equipment"

Dear Sir:

The following ini 3rmation is provided in response to Section 3.10 of SSER 4:

A.

Seismic ar.d Dynamic Qualification (SQRT) Items 1.

Sectian 3.10.1.3:

What is the status of the generic program for cabinet spacing?

Response: The program addressing cabinet spacing has been completed and modifications as required have been implemented.

2.

Section 3.10.1.5(2):

What is the status of the three-inch drain on the emergency feedwater pump turbine (BOP-5)?

Response: The three-inch drain was made permanent.

Information relative to this item was provided in SBN-997 (April 8, 1986), Attachment A, Item 5(a).

8606180001 860613 PDR ADOCK 0500 3

E Ao48 ll 0 Seabrook Station Construction Field Office. P.O. Box 700 Seabrook NH O3874

United States Nuclear Regulatory Commission Attention:

Mr. Vincent S. Noonan Page 2 8.

Operability Qualification of Pumps and Valves (PVORT) Items 1.

Section 3.10.2.3(2): This section concerns the cracked seal on auxiliary feedwater pump (FW-P-37A) and states the pump must be retested prior to fuel load to verify seal integrity'.

Response

Letter SBN-997 ( April 8,1986), Attachment A, Item 8(a), explained that the shaft seal was remachined to correct the mismatch of the shaft and seal. The retest of.the pump cannot be done prior to fuel load because the only steam supply to the pump is from the secondary side of the plant. The test will be conducted in conjunction with the startup test program, af ter core-load, but prior to initial criticality. The schedule for the retest has been discussed with Region I inspectors and found acceptable.

2.

Section 3.10.2.3(3):

This item is to confirm that the AUXILIARY FEEDWATER PUMP (FW-P-37A) turbine trip and throttle valve can be operated easily during an emergency condition.

Response

Letter SBN-1025 (May 1,1986) provides the results of tests which show that one man can operate the valve following an overspeed trip.

We expect that the program to reconcile generic g-loading of NSSS valves (SER Section 3.10.1.3), and the overall completion of the seismic qualification program (SER Section 3.10.2.3(5)], to be completed by June 30,1986. The NRC will be notified when these programs are complete..

We trust this information is acceptable and request the status of these items be reflected in the next supplement to Seabrook's SER.

Very truly yours, A

John DeVincentis Director of Engineering cc: Atomic Safety and Licensing Board Service List i

i I.

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Senator Cordon J. Humphrey H. Joseph Flynn, Esquire U.S. Senate Office of General Counsel Washington, DC 20510 Federal Emergency Management Agency (ATTN: Tom Burack) 500 C Street, SW l

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