ML18093A929
| ML18093A929 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/24/1988 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Miltenberger S Public Service Enterprise Group |
| References | |
| TASK-2.K.3.05, TASK-TM GL-83-10, GL-85-12, GL-86-05, GL-86-5, NUDOCS 8807110201 | |
| Download: ML18093A929 (6) | |
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June 24, 1988 Docket Nos. 50-272/311 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. Miltenberger:
SUBJECT:
GENERIC LETTER 85-12, "AUTOMATIC TRIP OF REACTOR COOLANT PUMPS 11
, TMI ACTION ITEM II.K.3.5 RE:
SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 In Generic Letter 85-12 (Ref. 1) we reported that the information provided by the Westinghouse Owners Group (WOG) in support of alternative Reactor Coolant Pump (RCP) trip criteria was acceptable on a generic basis.
The review noted that a number of considerations were assigned plant specific status.
Accordingly, we requested that operating reactor licensees select and implement an appropriate RCP trip criterion based upon the WOG methodology.
The staff has reviewed your response, dated October 4, 1985, and concluded that the information provided was acceptable.
Our SER is attached.
As such, no further plant specific action with respect to Generic Letter 85-12 is required.
Enclosure:
As stated cc w/enclosure:
See next page
._j DISTRIBUTION Docket File PDI-2 Reading BBoger M0 1Brien(2)
MThadani EJordan/BGrimes SWu Sincerely,
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Donald C. Fischer, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation MRC PDR/LPDR SVarga WButler DFischer OGC-WF ACRS (10)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket Nos. 50-272/311 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. Miltenberger:
June 24, 1988
SUBJECT:
GENERIC LETTER 85-12, "AUTOMATIC TRIP OF REACTOR COOLANT PUMPS", TMI ACTION ITEM II.K.3.5 RE:
SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 In Generic Letter 85-12 (Ref. 1) we reported that the information provided by the Westinghouse Owners Group (WOG) in support of alternative Reactor Coolant Pump (RCP) trip criteria was acceptable on a generic basis.
The review noted
.that a number of considerations were assigned plant specific status.
Accordingly, we requested that operating reactor licensees select and implement an appropriate RCP trip criterion based upon the WOG methodology.
The staff has reviewed your response, dated October 4, 1985, and concluded that the information provided was acceptable.
Our SER is attached.
As such, no further plant specific action with respect to Generic Letter 85-12 is required.
Enclosure:
As stated cc w/enclosure:
See next page Sincerely,
_(:, c~J e 1k>cL Donald C. Fischer, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Mr. Steven E. Miltenberger Public Service Electric & Gas Company cc:
Mark J. Wetterhahn, Esquire Conner and Wetterhahn Suite 1050 1747 Pennsylvania Avenue, NW Washington, DC 20006 Richard Fryling, Jr., Esquire Law Department - Tower SE 80 Park Place Newark, NJ 07101 Mr. John M. Zupko, Jr.
General Manager - Salem Operations Salem Generating Station P.O. Box E Hancocks Bridge, NJ 08038 Robert Traee, Mayor Lower Alloways Creek Township Muni ci pa 1 Ha 11 Hancocks Rridge, NJ 08038 Richard W. Borchadt, Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, NJ 08038 Richard F. Engel Deputy Attorney General Department of Law and Public Safety CN-112 State House Annex Trenton, NJ 08625 Mr. David M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection State of New Jersey CN 411 Trenton, NJ 08625 Salem Nuclear Generating Station Richard B. McGlynn, Commission Department of Public Utilities State of New Jersey 101 Commerce Street Newark, NJ 07102 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Bruce A. Preston, Manager Licensing and Regulation Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Morgan J. Morris, III General Manager - Operating License Atlantic Electric P.O. Box 1500 1199 Black Horse Pike Pleasantville, NJ 08232 Delmarva Power & Light Company c/o Jack Urban General Manager, Fuel Supply 800 King Street P.O. Box 231 Wilmington, DE 19899
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 SAFETY EVALUATION BY THF OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO IMPLEMENTATION OF TMI ACTION ITEM II.K.3.5 "AUTOMATIC TRIP OF REACTOR COOLANT PUMPS" (RESPONSE TO GENERIC LETTER NO. 85-12)
PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-272/311
- 1. 0
SUMMARY
In Generic Letter 85-12 (Ref. 1) we reported that the information provided by the Westinghouse Owners Group (WOG) in support of alternative Reactor Coolant Pump (RCP) trip criteria was acceptable on a generic basis. The review noted that a number of considerations were assigned plant specific status.
Accordingly, we requested that operating reactor licensees select and implement an appropriate RCP trip criterion based upon the WOG methodology.
This Safety Evaluation (SE) contains the staff's findings concerning this issue for Salem Nuclear Generating Station, Units 1 and 2.
Reference 1 required owners of Westinghouse Nuclear Steam Generating Systems to evaluate their plants with respect to RCP trip. The objective was to demonstrate that their proposed RCP trip setpoints assure pump trip for small break LOCAs, and in addition to provide reasonable assurance that RCPs are not tripped unnecessarily during non-LOCA events. A number of plant specific items were identified which were to be considered by applicants and licensees including the selected RCP trip parameter, instrumentation quality and redundancy, instrumentation uncertainty, possible adverse environments, calculational uncertainty, potential RCP and RCP associated problems, operator training, an_d operating procedures.
The licensee has addressed the Generic Letter 85-12 criteria and we have reviewed this information.
We find the material submitted by the licensee to be acceptable and find that the licensee has satisfied the requirements in regard to TMI Action Item II.K.3.5.
2.0 BACKGROUND
TMI Action Item II.K.3.5 of NUREG-0737 (Ref. 2) required all licensees to consider solutions pertinent to tripping RCPs under transient and Loss of Coolant Accident (LOCA) conditions. A summary of the industry and NRC programs concerning RCP trip was provided in SEC-82-475 (Ref. 3). Reference 3 also provided NRC guidance and criteria for resolution of II.K.3.5, and enclosed Generic Letters 83-10 (Ref. 4), which outlined requirements pertinent to RCP trip.
The WOG responded to Reference 4 by developing RCP trip criteria and provided information which individual utilities could use for plant-specific implementation (Ref. 5). The staff then issued Generic Letter 85-12 and directed each applicant and licensee to provide RCP trip criteria and substantiating information.
The licensee addressed this issue in Reference 6, which we have reviewed.
3.0 EVALUATION The staff finds that the licensee has complied with the requirements of Generic Letter 86-05 and that they have therefore met the requirements in regard to implementation of TMI Action Item II.K.3.5.
These requirements include:
A.
Determination of RCP Trip Criteria Salem Nuclear Generating Station has selected low RCS Pressure less than 1450 psig as the basic criteria for tripping the Reactor Coolant Pumps (RCP's) from the three options provided in (WOG) developed Emergency Response Guidelines, High Pressure Version.
For a Steam Generator Tube Rupture or non-LOCA event, reactor coolant subcooling less than l0°F (in addition to instrument uncertainties) is used to trip the RCP's.
We conclude these are acceptable.
Al.
Instrumentation Identification including Redundancy and Quality Level The licensee has identified all of the essential instrumentation and degree of redundancy used to trip the RCPs.
We conclude these are acceptable.
A2.
Instrumentation Uncertainties for Normal and Adverse Environments The licensee has demonstrated that the instrument uncertainties do not exceed the allowable limits specified by NRC.
We conclude these uncertainties are acceptable.
A3.
Analysis Uncertainties The licensee has demonstrated that the results of the WOG generic analyses are conservative for Salem Units 1 and 2.
Therefore, we consider these acceptable.
B.
Potential Reactor Coolant Pump Problems Bl.
Containment Isolation Impact Upon RCP Operation The licensee has demonstrated that the RCP water services can be restored following containment isolation.
We consider this acceptable.
- 82.
Components Required for RCP Trip Manual trip of the RCPs is accomplished from the main control room.
No critical components required to initiate manual RCP trip are located in a harsh environment.
We conclude that the licensee has provided an acceptable response to this item.
C.
Operator Training and Procedures The licensee has provided adequate operator training and procedures, which are consistent with the NRC staff guidelines.
We thus conclude these are acceptable.
- 4. 0 CON CL US ION Each of the points identified in Reference 1 has been satisfactorily addressed by the licensee.
Further, the licensee has considered items pertinent to RCP trip and operation which are in addition to the Reference 1 requirements.
The staff finds the licensee treatment of RCP to be acceptable and the licensee has satisfied the requirements of TMI Action Item II.K.3.5.
5.0 REFERENCES
- 1.
Hugh L. Thompson, Jr., "Implementation of TMI Action Item II.K.3.5,
'Automatic Trip of Reactor Coolant Pumps 11 (Generic Letter 85-12), June 28, 1985, Letter to all applicants an licensees with Westinghouse Nuclear Steam Supply Systems.
- 2.
"Clarification of TMI Action Plan Requirements," NUREG-0737, USNRC, November 1980.
- 3.
Dircks, William J., "Staff Resolution of the.Reactor Coolant Pump Trip Issue," Policy Issue for the Commissioners from the Executive Director for Operations, NRC, SECY-82-475, November 30, 1982.
- 4.
Eisenhu:t, Darrell G., "Resolution of TMI Action Item II.K.3.5, 'Automatic Trip of Reactor Coolant Pumps,' (Generic Letter No. 83-10)," letter to all applicants with (PWR vendor) designed nuclear steam supply systems from Director, Division of Licensing, NRC.
- 5.
Westinghouse Owners Group Letter OG-110, 11 Evaluation of Alternate RCP Trip Criteria, December 1, 1983.
- 6.
C. A. McNeill, Jr., Implementation of TMI Action Item II.K.3.5, 11Automatic Trip of Reactor Coolant Pumps, 11 Letter from C. A. McNeill, Jr., Vice President-Nuclear, to H. L. Thompson, Jr., Director, Division of Licensing, USNRC, October 4, 1985.