ML18093A509
| ML18093A509 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/25/1987 |
| From: | Corbin McNeil Public Service Enterprise Group |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NLR-N87221, NUDOCS 8712020256 | |
| Download: ML18093A509 (5) | |
Text
Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Senior Vice President -
Nuclear Public Service Electric and Gas Company P.O. Box236, Hancocks Bridge, NJ 08038 609 339-4800 November 25, 1987 NLR-N87221 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
APPENDIX R MODIFICATION SCHEDULE SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Pursuant to our discussions with Region I on October 7, 1987, attached is the schedule for hardware modifica~ions related to License Event Reports87-009 and 87-010.
Included in the schedule is a cross reference to the appropriate section of the Safety Evaluation provided on October 16, 1987.
The schedules presented herein represent the best estimate available at this time and may be subject to change based on the restart effort manpower requirements and hardware delivery times.
PSE&G will advise you of any significant modifications to the attached schedule.
Should there be any questions, please feel free to contact us.
Attachment 8712020256 871125 PDR ADOCK 05000272 F
PDR Sincerely,
Document Control Desk 2
C Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 11-25-87
LER 87-009 AND 87-010 MODIFICATION SCHEDULE The following is a compilation of items noted in Licensee Event Reports87-009 and 87-010.
The associated schedules are-at this time, the best estimates available and may be subject to change based upon restart effort manpower requirements and hardware delivery times.
For ease of comparison to Safety Evaluation S-C-M200-NSE-0709-l, the
- applicable sections of the safety evaluation are also noted.
Unit 1 numbers are indicated with the corresponding Unit 2 numbers shown parenthetically.
I.
LER 8 7-009 dbl/2 A.
UHF Communication System (Safety Evaluation Section 4.3}
The Design Change Package related to this modification is scheduled to be issued by Jan. 1, 1988.
Considering that parts delivery typically requires 8-10 weeks upon order receipt, implementation is not expected to begin before approximately April 15, 1988.
Therefore, the completed design change encompassing both units may not be reasonably expected until approximately July 1, 1988.
B.
- 11 (21} Fuel Oil Storage Room -
Fire Area 1(2}FA-DG-84D (Safety Evaluation Section 4.4}
Conduit 1(2}BDDA-B will be completely protected with a one-hour barrier throughout the area.
This will be accomplished as part of Design Change Package 1(2}EC-2248 which is currently scheduled for completion by April 15, 1988.
C.
Upper Electrical Penetration Area-Fire Area 1(2}FA-EP-100G (Safety Evaluation Section 4.5}
Conduit 1(2}RP65-AT will be completely protected with a one-hour barrier throughout the area.
As part of accomplishing this task, the conduit must be rerouted due to physical interferences associated with wrapping.
This will be accomplished as part of Design Change Package 1(2}EC-2248 which is currently scheduled for completion by April 15, 1988~
dbl/3 D.
C02 Equipment Room - Fire Area 1(2)FA-DG-84F (Safety Evaluation Section 4.6)
Raceway 1(2)A008 and Conduits 1(2)A4YG-A, 1(2)B3D~B, 1(2)B8D-B, 1(2)ADD-A, 1(2)ADDA-A, and 1(2)AGN-A will be completely protected throughout the area.
This will be accomplished as part of Design Change Package 1(2)EC-2248 which is currently scheduled for completion by April 15, 1988.
E.
Auxiliary Building, Elevation 64" - Fire Area 1(2)FA-AB-64B (Safety Evaluation Section 4.7)
The separation problem associated with Panel 119 does not impact the capability to achieve and maintain hot standby.
While maintaining hot standby, repairs could be performed and/or temporary ventilation established for the Residual.Heat Removal areas.
Consequently, this modification is not as critical as those previously noted.
The Panel 119 situation is currently under evaluation.
As such, the physical modification will be dependent upon the results of the evaluation, currently scheduled.for completion by December 1, 1987.
The options will include, at the extremes, either eliminating the panel and locking the dampers in position, or providing an additional redundant panel including the required rewiring, rework of the control air piping, and the appropriate fire barrier protection.
In the worst case, the modification could be expected to be completed by July 1, 1988.
F.
Pipe Tunnel -
Fire Area 12FA-PT-84 (Safety Evaluation Section 4.8)
A fire detection system will be provided for the Pipe Tunnel as part of Design Change Package 2EC-2251A.
This modification will require a significant length of new cabling and possible core bores.
As such, it is currently scheduled for completion by May 1, 1988.
G.
Spurious Actuation of C02 in the Diesel Generator Rooms (Safety Evaluation Section 4.9)
This concern is presently being investigated in more detail.
A more accurate model of the Diesel Generator rooms is currently being developed and
analyzed.
Results are expected by Dec. 15, 1987.
Any potential modifications are expected to be implemented by July 1, 1988.
II.
LER 87-010 Diesel-Generator Fuel Oil Transfer Pumps dbl/4 Design Change Package 1(2)EC-2284 has been issued.
Delivery of parts is pending.
Implementation is expected by March 1, 1988.