ML17325A879
| ML17325A879 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/13/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325A878 | List: |
| References | |
| TASK-2.K.3.05, TASK-TM GL-85-12, NUDOCS 8807190379 | |
| Download: ML17325A879 (3) | |
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UNITEDSTATES NUCLEAR REGULATORYCOMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE 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)
INDIANA MICHIGAN POWER COMPANY DONALD C.
COOK NUCLEAR PLANT UNITS NOS.
1 AND 2 DOCKETS NOS. 50-315 AND 50-316 1.0
SUMMARY
In Generic Letter 85-12 (Ref.
- 1) the staff reported that the information provided by the Westinghouse Owner s 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, the staff requested that operating reactor licensees select and impleIIIent an appropriate RCP trip criterion based upon the WOG methodology.
This Safety Evaluation (SE) contains the staff's findings concerning this issue for Donald C. Cook, 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, and operating procedures.
The licensee has addressed the Generic Letter 85-12 criteria, and the NRC staff has reviewed this information.
The staff finds the material submitted by the licensee to be acceptable and that the licensee has satisfied the requirements in regard to TMI Action Item II.K.3.5.
2.0 BACKGROUND
TMI Action Plan 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 SECY-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.
8807190379 SS0713 PDR ADOCK 05000315 P
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 NRC 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 the staff has reviewed.
- 3. 0 EVALUATION The NRC staff finds that the licensee has complied with the requirements of Generic Letter 85-12 and that it has 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 The RCPs will be tripped if the indicated RCS pressure is less than 1250psig for both normal and abnormal containment conditions.
This setpoint is contained in the Emergency Operating Procedures.
This agrees with WOG guidelines and hence is acceptable.
A1, Instrumentation Identification including Redundancy and equality Level The licensee has identified all of the essential instrumentation and degree of redundancy used to trip the RCPs.
The staff concludes 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.
The staff concludes these uncertainties are acceptable.
A3.
Analysis Uncertainties The licensee has demonstrated that the results of the WOG generic analyses are conservative for D.C.
Cook.
Therefore, the staff considers 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.
The staff considers this acceptable.
B2.
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.
The staff concludes 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.
The staff thus concludes these are acceptable.
4.0 CONCLUSION
Each of the points identified in Reference I 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 I requirements.
The staff finds the licensee treatment of RCP to,be acceptable, and the licensee has satisfied the requirements of TNI Action Item II.K.3.5.
5.0 REFERENCES
1.
Hugh L. Thompson, Jr.,
"Implementation of TYiI Action Item II.K.3.5,
'Automatic Trip of Reactor Coolant Pumps'Generic Letter 85-12),
June 28, 1985, letter to all applicants and licensees with Westinghouse Nuclear Steam Supply Systems.
2.
"Clarification of TRI Action Plan Requirements,"
NUREG-0737, US NRC 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.
Eisenhut, Darrell G., "Resolution of TYiI 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.
5.
Westinghouse Owners Group Letter OG-110, "Evaluation of Alternate" RCP Trip Criteria, Dec.
1, 1983.
6.
Yi. P. Alexich, "Response to Generic Letter No. 85-12", Indiana and Michigan Electric Company, November 27, 1985.
Principal Contributor:
S.L, Wu