ML18086A272
| ML18086A272 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/16/1981 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8104210311 | |
| Download: ML18086A272 (7) | |
Text
-
PS~G Public Service Electric and Gas Company _80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 April 16~ 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 NO. 50-311 Public Service Electric and Gas Company hereby submits; in to this letter; an updated Q list.
This list has been updated in response to your February 27~ 1981 letter and supersedes the Q list submitted by letter dated September 8, 1980.
Justification is provided in Enclosure 2 for items identified in your letter and not included in our Q list.
Should you have any questions in this regard, please do not hesitate to contact us.
FAM:mlr Very truly yours~
R. L. Mittl General Manager -
Licensing and Environment Encl.
CC:
Mr. Leif Norrholm Senior Resident Inspector
'Bool
.s CL02/l 1/t p
95-0942
ENCLOSURE 1 Q 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 items 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.
- 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, Accumulators, 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/l 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 filters and moisture separators).
- 5.
Service Water System (entire system serving the nuclear portion of the plant, as shown in FSAR Figure 9.9-1)
- 6.
Auxiliary Building Ventilation System (supply and exhaust units)
- 7.
Fuel Handling Building Ventilation System (exhaust units)
- 8.
Auxiliary Feedwater Storage 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, govrnor, 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 System (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
)a._.. ** 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 Table Q7.18-l (response to Question 7.18)
- 33.
Spent Fuel Pool Cooling System
- 34.
Meteorological Data Collection Program
- 35.
- 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 in this 1 ist.
- 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.
4/15/81 M P80 81 14 1/4
ENCLOSURE 2 Following is a one-to-one discussion of the items listed in the NRC "Request for Additional Information" letter.
Justi-fication is provided for not including some of these items in our Q list.
- 1.
Items from Request for Information 260.1.a Items 1, 4, 5, 6, 7, 8, 9, 10, 11, and 12 are covered by Regulatory Guide 1.33, Appendix A, and ANSI Nl8.7, to which PSE&G is already committed in the FSAR, Pages D.2-12 and D.2-13.
This includes the equipment in-volved as well as the activities of calibration, use and storage.
Also, Items 4 and 5 are covered by Item 25 of the Q list: NRC Item 6 is covered by Item 16 of the Q 1 ist.
NRC Item 2 (Masonry Walls) is covered by Regulatory Guide 1.29 to which PSE&G is already committed.
NRC Item 3 is covered by Items 3 and 39 of the Q list.
- 2.
As stated in the introduction to the Q list (Enclosure 1), the OPQA Program will be applied to all items on the Q list 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 designed and constructed under the QA Program are so identified elsewhere in the FSAR.
Justifications for items in Request for Information 260.1.b:
Item 1 is not covered by the QA program.
All safety-related information is displayed and actions are per-formed from the Control Room.
Item 2 is covered by Item 2 of the Q list (systems and components)
- Item 3 has been added to the Q list.
All analyses and design modifications will be covered by the QA Program.
Item 4 is covered by Item 16 of the Q list and by compliance with Regulatory Guide 1.33, Appendix A.
Item 5 is covered by Items 26 and 27 of the Q list.
Item 6 is covered by Item 15 of the Q list.
Item 7 is covered by Item 15 of the Q list.
Item 8 has been added to the Q list.
FAM:mlr
- Item 9 does not apply to Salem Nuclear Generating Station, which does not have dedicated hydrogen penetrations.
Item 10 is covered by Item 30 of the Q list.
Item 11 has been added to the Q list.
Item 12 has been added to the Q list.
Item 13 is covered by Item 12 of the Q list.
Item 14 is not applicable.
The Salem Station has manual PORV isolation at this time.
If the studies specified in the TMI Action Plan determine that automatic PORV isolation is needed, this item will be added to the Q list.
Item 15 -
same as Item 14 above.
Item 16 was covered by our response to NUREG-0660.
Any future modification will be effected under the QA Program.
Item 17 has been added to the Q list.
Item 18 is covered by Item 12 of the Q list.
Item 19 -
the Salem Emergency Plan has been added to the Q list.
Item 20 is not covered by the QA program.
All safety related information is displayed and actions are performed from the Control Room.
Item 21 -
the portable equipment is covered by compliance with Regulatory Guide 1.33, Appendix A.
The fixed equipment is covered by Item 25 of the Q list.
Item 22 is covered by Item 24 of the Q list.
CL02 2/3