ML18092A259
| ML18092A259 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/15/1984 |
| From: | Liden E Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.05, TASK-TM GL-83-10D, NUDOCS 8408240117 | |
| Download: ML18092A259 (5) | |
Text
....,.... -.
e
- ops~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department August 15, 1984 Director of Nuclear Reactor Regulation
- u. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014 Attention:
Mr. Steven Varga, Chief Operating Reactors, Branch 1
Dear Mr. Varga:
RESOLUTION OF TMI ACTION ITEM II.X.3.5 AUTOMATIC TRIP OF REACTOR COOLANT PUMPS SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 PSE&G hereby submits its plan for resolution of TM! Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps.
The attached text supplements our response, dated April 22, 1983, to Generic Letter 83-lOd.
This submittal in conjunction with the implementation of Revision 1 to the Emergency Response Guidelines will complete our response to this TM! Action Item.
Should you have any questions, please contact us.
Sincerely, E. A. Liden Manager -
Nuclear Licensing and Regulation Attachment (all)
The Energy People fl() l/-6
'/ /
95-2168 (80 M) 11-82
Mr. Steven C Mr. Donald C. Fischer Licensing Project Manager Mr. James Linville Senior Resident Inspector 8/15/84
SALEM NUCLEAR POWER STATION RESOLUTION OF TMI ACTION ITEM II.K.3.5 "AUTOMATIC TRIP OF REACTOR COOLANT PUMPS" Our previous letter dated April 22, 1983, presented the plan for demonstrating compliance 'with the criteria for resolution of TMI Action Plan Item II.K.3.5 which were established in letters from Mr. Darrel G. Eisenhut of the Nuclear Regulatory Commission to all Applicants and Licensees with Westinghouse designed Nuclear Steam Supply Systems (83-lOc and d) dated February 8, 1983.
This letter summarizes Salem's subsequent actions to resolve this concern.
Section I of the attachment to NRC letters 83-lOc and d is concerned with "Pump Operation Criteria Which Can Result in RCP Trip During Transients and Accidents."
Subsection 1 of Section 1 presents guidelines for establishing setpoints for RCP Trip.
The Westinghouse Owners Group response to this section of NRC Letters 83-lOc and d is contained in Revision 1 to the Generic Emergency Response Guidelines (ERGs) which has been approved and issued.
The tentative schedule for incorporating Revision 1 of the Generic ERGs to the Salem Specific Procedures is:
Salem Specific Procedures Revised -
Sept. 1, 1984 Operator Training -
Sept. 84 through Feb. 85 Implementation of Revised Procedures -
March 1, 1985 The RCP Trip Criterion being adopted in the Salem specific procedures not only assures RCP trip for all losses of primary coolant for which trip is considered necessary but also permits RCP operation to continue during most non-LOCA accidents, including steam generator tube rupture events up to the desgin basis double-ended tube rupture.
The generic applicability of the RCP Trip criterion selected has been documented by the Westinghouse Owners Group in "Evaluation of Alternate RCP Trip Criteria", September, 1983, which was submitted to the NRC for review by letter OG-110, dated December 1, 1983 (Sheppard to Mattson).
The parameter selected for the RCP trip setpoint at Salem is the Reactor Coolant System pressure.
Specifically, the instrumentation which will be monitored is the Reactor Coolant System wide range pressure.
Wide range presssure is monitored through two redundant, safety related channels.
Each channel uses a seismically and environmentally qualified Rosemount Transmitter, model 1153GD9 (Refer to PSE&G E.Q. Report No. 49, Wyle Laboratory Report 45592-3).
FI17 2
The Salem procedures will be implemented after the operators train with the new procedures using the simulator.
This will at the same time, allow for timely identification and resolution of any procedural problems prior to actual implementation.
Training has already been conducted to instruct the operators on the responsibility to trip RCPs during small break LOCAs.
Subsection 2 of Section 1 of the attachment to NRC Letters 83-10 c and d provides guidance for justification of manual RCP trip.
Subsection 2a requires that compliance with 10CFR50.46 be demonstrated in an Appendix K small break LOCA analysis given that the RCPs are tripped two minutes after the onset of reactor conditions corresponding to the RCP trip setpoint.
The Westinghouse Owners Group has submitted to the NRC, via letter OG-117, dated March 12,1984, the report entitled "Justification of Manual RCP Trip for Small Break LOCA Events".
This report has generically verified that predicted LOCA transients presuming the two minute delayed RCP trip are nearly identical to those presented in Safety Analysis Reports utilizing the WFLASH Evaluation Model.
Thus, the final Safety Analysis Report for Salem demonstrates its compliance with the Subsection 2a guidelines.
The WOG has also performed most probable, best estimate, WFLASH analyses to demonstrate, generically, complience with the guidelines presented in Subsection 2b of Section I of the attachment to NRC Generic Letters 83-lOc & d.
These analyses identify that the minimum time available for operator action for the complete range of LOCA break sizes exceeds the value contained in Draft ANSI Standard N660; they show that reactor coolant pumps may be tripped at any time during a LOCA event without resulting in excessive clad temperatures.
The applicability information presented in the generic report affirms the applicability of this best estimate analyses to Salem.
Therefore, in combination with the Subsection 2a justification cited above, the best estimate analyses justify that manual RCP trip is acceptable for Salem when RCP trip setpoints consistent with Revision 1 to the Emergency Response Guidelines are in use.
Furthermore, the generic report demonstrates that no additional contingency emergency procedures are required to address the scenarios which may follow a missed RCP trip setpoint.
FI17 3
In summary, the generic information presented by the Westinghouse owners Group in the reports entitled "Evaluation of Alternate RCP Trip Criteria" and "Justification of Manual RCP Trip for Small Break LOCA Events" provides the response to NRC Generic Letters 83-lOc and d for Salem.
The implementation of Revision 1 to the Emergency Response Guidelines in the plant specific procedures with an appropriate RCP trip setpoint specified resolves all issues associated with automatic tripping of the reactor coolant pumps.
Fll 7 4