ML18086A475

Forwards Updated Q-list

ML18086A475
Person / Time
Site:	Salem
Issue date:	05/12/1981
From:	Mittl R Public Service Enterprise Group
To:	Miraglia F Office of Nuclear Reactor Regulation
References
NUDOCS 8105140096
Download: ML18086A475 (5)

Text

,...

0 PS~G*

Public Service Electric and Gas Company 80 Park Plaza, Tl 60 Newark, N.J. 07101 201/430-8217 Robert L. Mitt!

General Manager - Licensing and Environment May 12, 1981 Director of Nuclear Reactor Regulation

u. s. Nuclear Regulatory Commission Washington, D.. c..

20555 Attention:

Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing Gentlemen:

UPDATED "Q" LIST NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET N.O. 50-.3.11 Public Service Electric and Gas Company hereby submits,.in the enclosure to this letter, an updated "Q" lis.t.,

As a result of our telephone conversation with Mr& Jack Spraul of the NRC staff, item 49 and 50 have been added to the "Q" list.

This list therefore supersedes the "Q" list submitted by letter dated April 16, 198.1.

Should you have any questions in this regard, please do not hesitate to contact us~

Enclosure CC:

Mr. Leif Norrholm Very truly yours, Senior Resident Inspector rs 10.514. o D'lv p

The Energy People I~

ENCLOSURE 1 0 LIST -

OPERATIONS PHASE

---

- --------------~----------.

The listing below identifies those structures, systems and components to which the Operational Quality Assurance (OPQA)

Program applies, as described in FSAR Appendix D, Section D. 5. 2.

The OPQA Program will be applied to these i terns.,

through the operations phase.

Not all of these items were designed and constructed under the QA program and will not be backfitted in this regard.

Those items that were de-signed and constructed under the QA program are so identi-fied elsewhere in the FSAR.

Structures

1.

Containment (including penetrations, concrete shielding, interior structures, air locks, equipment hatch)

2.

Fuel Handling Building 3~

Auxiliary Building (including Control Room and Diesel Generator Area).

4.

Service Water Intake Structure systems and Components

1.

Reactor Protection System

2.

Reactor (including vessel, supports, intervals, fuel assemblies, RCC assemblies and drive mechanisms, sup-porting and positioning members, and in-core instrumen-tation)

3.

Reactor Coolant System (including piping, valves, steam generators, pressurizer, safety and relief valves, block valves, piping to pressurizer relief tank, reactor coolant pumps, and supports)

4.

Engineered Safety Features

. A.

ECCS (including Safety Injection and RHR pumps, RWST, 1Accumulators, RHR Heat Exchangers, containment sump, sump screen, vortex suppression devices, and connecting piping and valves)

B.

Containment Spray System (including Spray pumps, spray headers, spray additive tank, connecting pip-ing and valves)

M P80 81 14/1

• C.

Portions of the CVCS (including Centrifugal Charging_

pumps, Boron Injection Tank, connecting piping and **

valves).

D.

Containment Ventilation System (including fan coolers, distribution ducts, dampers, HEPA fiiters and moisture separators).

5.

Service Water System (entire system serving th*e nuclear*

portion of the plant, as shown in FSAR Figure 9.9-~).

6.

Auxiliary Building Ventilation System (supply and exhaust units)

7.

Fuel Handling Building Ventilation System (exhaust units) 8~

Auxiliary Feedwater Storaqe Tank

9.

Residual Heat Removal System

10.

Component Cooling System

11.

Fuel Transfer Tube

12.

Emergency Power Supply Systems A. Diesel Generators (including associated fuel oil,

.lub oil, starting auxiliary systems, fuel storage and day tanks, jacket cooling, qovrnor, voltage, regulatory and excitation systems)

B. Diesel Generator Area Ventilation System C. DC Power Supply System D. Power distribution lines to equipment required for emergency transformers and switchgear supplying En-gineered Safety Features (includes 4 kV, 460V and 230V vital buses).

E. Control Boards and Motor Control Centers F. Control equipment, facilities and lines required for above items M P80 81 14/2

• 13.

Waste Disposal Systems A. Gas Decay Systems B. Compressor

14.

Containment Polar Crane

15.

Auxiliary Feedwater System

16.

Sampling System (to outermost containment isolation valve)

17.

Main Steam S~stem (to isolation valve)

18.

Feedwater System (to outermost isolation valve)

19.

Hydrogen Recombiners, hydrogen analyzers, and supports.

20.

Fuel Handling System

21.

Switchgear Room Ventilation System

22.

Steam Generator Blowdown System (to outermost containment isolation valve)

23.

Containment Pressure -

Vacuum Relief System

24.

Control Area Air Conditioning System

25.

Radiation Monitoring System (those portions required for Class I equipment and systems)

26.

Process Instrumentation and Controls (those portions*

required for Class I equipment and systems)

27.

Instrumentation and Control Systems required for safe shutdown (including safety related instrumentation)

28.

Electrical Cable Tunnels

29.

Control Panels - Class IE circuits

30.

All systems which penetrate containment, up to' and including the containment isolation valve (identified in FSAR Section 5.4)

M P80 81 14/3

• 31.

Instrument Air System (including accumulators, inter-:

connecting piping and valves) for air-operated* valves that perform a safety function.

32.

Safety Related equipment identified in FSAR TaQle Q7.18--1 (response t_o Question* 7.18)

33.

Spent Fuel Pool Cooling System

34.

Meteorological Data Collection Program

35.

~ire Protection Program

36.

Leakage Detection System (as discussed in FSAR Sec-tion 4.2.7.).

37.

Missile Barriers (protecting safety-related equipment).

38.

Shoreline Dike (for protection against excessive wave action).

39.

Valve operators for all valves incorporated i.n this.

list.

40.

AC control power buses and inverters.

41.

Expendable and consumable items necessary* for the func-tional performance of critical structures, systems and components (i.e., weld rod, boric acid, fuel oil, etc.). -

42.

Nuclear Instrumentation System.

43.

Plant Shielding.

44.

Emergency Power for Pressurizer Heaters.

45.

Accident Monitoring Instrumentation.

46.

Instrumentation for detection of inadequate core-cooling.

47.

Anticipatory reactor trip on turbine trip.

48.

• Station Emergency Plan.

49.

Safety Parameter Display Console (instrument calibra-tion anq verification of functionalitx only).

SO.

Emergency Support Facilities (document control and verification of functionality only).

5/12/81 M P80 81 14 114