ML19320B530
| ML19320B530 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/12/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| TAC-42227, NUDOCS 8007140410 | |
| Download: ML19320B530 (1) | |
Text
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,#gp 58%c,A UNITED STATES 4 :HQ NUCLEAR REGULATORY COMMISSION LPOR-f a
all RYAN P IVE,SulTE 1000 2
AnUNGToN, TEXAS 76012 NSIC June 12, 1980 Docket Mo. 50-298 s
Nebraska Public Power Dittrict ATIN:
J. M. P11 ant, Director Licensing & Quality Assurance J
P. O. Box 499 Columbus, Nebraska 68601 Gentlemen:
Enclosed is IE Bulletin No. 80-14 which requires action by you with regard to your power reactor facility with. an. operating license, i
In order to assist the NRC in evaluating the value/ impact of each Bulletin on licensees, it would.be helpful if you would provide an est1 mate of the manpower expended in conduct of the review and preparation of the report (s) requi:.ed by the Bulletin. Please estimate separately the manpower associated with corrective actions necessary following identification of problens through the Bulletin.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, e'
1 V. Seyfr1t Director
Enclosures:
1.
L1at of Recently Issued I
I3 Bulletinc l
ec:
L. C. Lessor, Superintendent Cooper Nuclear Station Post Office Box 98 3rownville, Nebraska 68321 l
8007140 //jp
s SSINS No.:
6820 Accession No.:
UNITED STATES 8005050056 NUCLEAR REuULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT PASHINGTON, D.C.
20555 n'D S
- A Jin. ]ha' June 12, 1980 1E Bulletin No. 80-14 DEGRADATION OF BWR SCRAM DISCHARGE VOLUME CAPABILITY During our review of BWR operating experience, two events have raised concern on operations related to the control rod drive system scram discharge volume (SDV).
Description of Circumstances:
At Hatch Unit 1, on June 13, 1979, while performing surveillance to func-tionally test SDV high level switches, two switches (C11-N013 A, B) were found to be inoperable. Redundant switches (C11-N013 C, D) were operable. The i
reactor was in the refuel mode and these switches had been modified prior to this occurrence.
Inspection of the inoperable level switches revealed that the float rod was bent and binding against the side of the float chamber on both switches.
The licensee believes that the float rods were bent during or prior to initial installation and that metal particles from the modification caused binding of the float.
(LER 79-038)
Brunswick Unit 1. reported that slow closure of the SDV drain valve during a reactor scram on October 19, 1979 apparently caused a water hammer event which damaged several pipe supports en the SDV drain line.
Drain valve closure time l
was approximately five minutes due to a faulty solenoid controlling air supply to the valve. The damaged pipe supports were repaired but repair parts for the faulty solenoid were not available. To prevent possible damage from a scram, the unit started up with the SDV vent and drain valves closed except for periodic draining. During this mode of operation the reactor scrammed from high lesel in the SDV, without prior actuation of either the high level alarm or rod block switch.
Subsequent inspection revealed that the float ball on the rod block switch was crushed and the float ball stem on the high level alarm switch was bent such that the switches would not operata.
The water
?
hammer event discussed above was the reported cause of failure of these two switch assemblies.
(LER 79-74)
.As a result of these events and related anticipated transients without scram (ATWS) studies, concern arises that the SDV function may be degraded by the undetected presence of fluid in the SDV. The second event is significant in that it indicates the potential for a common cause failure ('aulty solenoid) to result in operation of the SDV in a manner which could defeat both the level switch function and the SDV draining function.
The ATWS generic studies
IE Bulletin No. 80-14 June 12, 1980 Page 2 of 3 (NUREG 0460) have led the staff to propose, among other requirements, improve-ments in the SDV designs to reduce susceptibility to common cause failures.
By separate correspondence, the staff will provide example Technical Specifica-tions related to the action items discussed below.
A.
GE BWR's With an Operating License The following actions are to be taken by licensees of GE designed BWR facilities with an operating license:
1.
Review plant records for instances of degradation of any SDV level switch which was or may have been caused by a damaged or bent float assembly.
Identify the cause and corrective action for each instance.
2.
Review plant records for instances of degradation of SDV vent and drain valve operability.
Provide the closure times required and typically observed for these valves and the basis for the required closing times.
4 Identify the cause and corrective action for each instance of degradation.
3.
By procedures, require that the SDV vent and drain valves be normally operable, open and periodically tested.
If these valves are not operable or are closed for more than I hour in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period during operation, the reason shall be logged and the NRC notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Prompt Notification).
4.
Review instances in which water hammer or damage which may have been caused by water hammer has occurred in SDV related piping.
Identify the eause and corrective action for each instance.
5.
Review surveillance procedures to ensure that degradation of any SDV level switch due to a damaged float or other cause wouLi be detected and that inoperability from any cause would be reported to the NRC.
6.
If no functional test or inspection which would detect degradation of each SDV level suitch has been performed during the past 3 months, make provisions to perform an inspection and functional test of all SDV level switch assemblies at the next reactor shutdown of greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> duration.
B.
Reporting Requirements The action taken in response to the items in Part A shall be completed and a written report on the results submitted to the NRC within 45 days from the date of this Bulletin.
l t
IE Bulletin No. 80-14 June 12, 1980 Page 3 of 3 This report should be submitted to the Director of the appropriate NRC Regional Office and a copy should be forwarded to the NRC Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D.C.
20555.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
Approval was given under a blankat clearance specifically for identified generic problems.
1 1
IE Bulletin No. 80-14 June 12, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-07 BWR Jet Pump Assembly 4/4/80 All GE BWR-3 and BWR-4 Failure facilities with an Operating License (OL) 80-08 Examination of Containment 4/7/80 All power reactors with a Liner Penetration Welds Construction Permit and/or Operating License (OL) 80-09 Hydramotor Actuator 4/17/80 All power reactor Deficiencies operating facilities and holders of power reactor construction permits (cps) 80-10 Contamination of 5/6/80 All power reactor Nonradioactive System and facilities with an Resulting Potential for Operating License (OL)
Unmonitored, Uncontrolled or Construction Permit Release to Environment (CP) 80-11 Masonry Wall Design 5/8/80 All power reactor facilities with an Operating License (OL),
except Trojan and holders of a Construction Permit (CP) 80-12 Decay Heat Removal System 5/9/80 Each PWR with an Operability Operating License (OL) 80-13 Cracking In Core Spray 5/12/80 All BWR's with an Operating License (OL)
Enclosure n