ML20011A175
| ML20011A175 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/01/1981 |
| From: | Bordine T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20011A176 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8110080106 | |
| Download: ML20011A175 (2) | |
Text
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Consumers POW 8f Company Generet offices: 212 West M6chleen Avenue, Jackse. MI 49201 e (617) 788-o550
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October 1, 1981 3 '
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Director, Nuclear Reactor Regulation h
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Att Mr Dennis M Crutchfield. Chief cg/ [
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US Nuclear Regulatory Commission 3
Washington, DC 20555
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DOCKET 50-155 - LICENSE DPR BIG ROCK
'O POINT PLANT - NUREG-0737, ITEM II.D.1, PERFORhANCE TESTING OF BWR RELIEF AND SAFETY VALVES By letter dated July 9,1981, Consuners Power Company provided an update of our response to NUREG-0737, Item II.D.1 " Performance Testing of Boiling Water Reactor and Preasurized Water Reactor Relief and Safety Valves," for Big Rock Point.
Specifically, our response committed a final summary report to be submitted by October 1, 1981 to include the following items:
1.
The results of the safety valves tests performed at Wyle Laboratories 2.
Confirmation that the results are valid 3.
Recommendations, if any, concerning the safety valves.
This letter and its enclosure provides the test results of the safety valves.
It does not include the confirmation that the test results are indeed valid for the Big Rock Point safety valves. This confirmation requires certain information from the valve supplier (Crosby Valve and Ga;,e Co).
Crosby has not been able to prepare this information due to manpower limitations resulting from their involvement in the EPRI safety and relief valve test program. We expect to be able to submit the required confirmation by the first quarter of 1982. Ilowever, Consumers Power Company has reviewed the characteristics of the test valve and determined that it is sufficiently similar to the Big Rock Point safety valves to conclude with reasonable certainty that the test is valid for Big Rock Point.
The test conducted at Wyle Laboratories were witnessed by technical represen-tatives from Wyle Laboratories, Dairyland Power Cooperative, Consumers Power Company and Crcsby Valve and Gage Company. The results of these tests are sununarized in the enclosed test report. The test results indicate that the valve operated satisfactorily during the test.
The test conditions were selected to simulate expected in-reactor operating conditions. Acceptance criteria for the safety valve performance tests were as follows:
the valve should oper., pasa desired steam *;10w, and reclose on demand.
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I Dennis M Crutchfield,' Chief 2
Big Rock Point Plant-October:1, 1981 relating to discharge piping and supports were established due to the fact that the Big Rock Point valves discharge through only a very short pipe elbow.
Thus, discharge pipe integrity is of no concern at Big Rock Point.
Nessured steam flow for one particular test (#14) was 194,000 lba/hr. The measured flow was less than the design capacity of the valve (302,000 lbm/hr) at the test pressure due to the fact that full valve lift was not achieved in the testing. As the design overpressure for the valve is 10% of setpoint, the test facility.did not have sufficient capacity to permit attaining full lift.
It should be noted that full valve lift is not to be expected during any anti-cipated operational' transients at Big Rock Point. Calculations have shown that the first relief valve will not lift for several minutes following reac-tor scram, and that a relief valve will anly 1 tit if the emergency condensor fails to operate. At the point of opening, the rate of pressure rise is expected to be so small that only one of the six valves (each of which has a rated capacity of approximately 35% of normal steaming rate) is more than adequate for relieving system pressure. However, for Anticipated Transient Without Scram-(ATW5) events, full lift of approximately four of six valves may occur. based on previous analysis in the Final Hazards Summary Report.
As stated, the test valve performed satisfactorily in terms of the test acceptance criteria. Minor adjustments, however, were made to the test valve 1
nozzle and guide ring settings to obtain optimum performance. The tests are being reviewed by Crosby to determine if adjustments should be made to the Eig l
Rock Point safety valves. Required adjustments, if any, will be described in the aforementioned submittal of information pertaining to test validity. Any necessary adjustments will be made as the Big Rock Point valves are reconditioned in accordance with ASME Boiler and Pressure Vessel Code Section XI IWV Testing Requirements.
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e Thomas C Bordine Staff Licensing Engineer CC JGKeppler, USNRC NRC Resident Inspector
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