ML19210E274
| ML19210E274 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/21/1979 |
| From: | Reeves E Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912040218 | |
| Download: ML19210E274 (6) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION C
WASHINGTON, O. C. 20555 5
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l November 21, 1979
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Occket No. 50-348 LICENSEE: Alabama Power Company FACILITY: Farley Nuclear Plant
SUBJECT:
SUMMARY
OF NOVEMBER 16, 1979 PHONE CONVERSATION REGARDING LESSONS LEARNED IMPLEMENTATION During a phone conversation on November 16, 1979 the NRC Lessons Learned Implementation Team discussed with the licensee, its October 24, 1979 response to our September 13, 1979 letter.
The team informed the licensee of those lessons learned items for which the licensee's proposed schedule for implementation is unacceptable. These items, along with the proposed and required completion dates, are listed in Enclosure 1.
The team informed the licensee of those items for which the proposed action does not appear to comply with the lessons learned requirement. These items and their associated deficiencies are listed in Enclosure 2.
The team also informed the licensee of those items for which further clarification of the licensee's comitment is necessary to demonstrate compliance with the lessons learned requirements. These items and the associated team questions are listed in Enclosure 3.
Items 2.1.3.b (Instrumentation for Detectic1 of Inadequate Core Cooling) (Procecures only), 2.1.7.a (AFW Initiation), 2.1.7.b (AFW Flow), 2.1.9 (Accident and Transient Analysis) were not discussed since these items are being implemented by the Bulletin and Orcers Task Force.
By letter dated October 30, 1979 we provided additional clarification of the lessons learned requirements to all licensees. We also requested tnat within 15 days licensee's justify proposed actions not in ccmplete agreement witn the staff's requirements and improve the implementation schedule where it differed from the staff's requirements. During this phone conversation we informed the licensee that those items listed in Enclosure 1 and 2 should be addressed in their respo.ise.
In addition, the licensee agreed to provide the information requested in Enclosure 3 in its response to our October 30, 1979 letter or as soon thereafter as possible.
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.Q m.n c A-8+w.-O cdward A. Reeves, Project Manager Operating :leactors Brancn
- 1 Division of Ope.ating Reactors Enclosure (3):
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.! enclosures: See next page
9 ENCLOSURE 1 ITEMS THAT 00 NOT MEET LESSONS LEARNED IMPLEMENTATION SCHEDULE 1.
SECTION 2.1.3 (a) - Direct Positive Indication of values APC should review and comply with the NRC clarification letter of October 30, 1979, particularly the implementation schedules and requiremtrits for alarms in the control room and seismic and c.nvironmental qualifications.
2.
SECTION 2.1.3 (b) - Instrumentation for Detection of Inadequate Core Cooling The required implementation date for installation of the subcooling meter is January 1, 1980.
3.
SECTION 2.1.4 - Containment Isolation Provisions The results of the investigat')n to identify essential and non-essential systems to the ARC no later than January 1, 1980.
4 SECTION 2.1.6.a - Intiarity of Systems The January 1,1980 program summary report should include lists of systems included and of systems excluded as well as a description of the procedures for reducing leakage. The report should include leak rate measurements.
5.
SECTION 2.1.3.a - Post-Accident Samoling The required date for completion of modification is January 1,1981.
The sample analysis capability should include determination of Hydrogen gas concentration in the containment atmosphere and for measuring disolved gases (i.e. H, 0 ) in the reactor coolant.
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ENCLOSURE 2 FARLEY l ITEMS THAT 00 NOT APPEAR TO COMPLY WITH LESSONS LEARNED REQUIREMENTS 1.
Containment Pressure The present containment pressure indication does not satisfy the NRC s+.aff requirement. Measurement and indication capability shall include three times the design pressure of the containment for concrete, four times the design pressure for steel, and minus five PSIG for all containments.
This range is provided so that containment pressure conditions can be monitored in the event that containment integrity is maintained even though the internal containment pressure may have exceeded design limits.
2.
Reactor Coolant System Vents APC indicated that it will make a decision on instal?ation of reactor coolant system vents based on conclusions reached as a result of analyses on detection of inadequate core cooling. The NRC staff pointed out that this analysis will not directly address the advisability of installing the vents or not installing the wents. Our position is that the vents should be installed to provide this capability to vent hydrogen and non-condensible gases if these degraded core cooling conditions are reached.
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ENCLOSURE 3 CLARIFICATION OF PROPOSED ACTIONS ARE NEEDED TO VERIFY COMFORMANCE TO LESSONS LEARNED REOUIREMENTS 1.
SECTION 2.1.3 (b) - Instrumentation for Detection of Inadequate Core Cooling and SECTION 2.2.1 (b) - Shift Technical Advisor (STA)
APC should review the requirements of the NRC staff position on these items as delineated in NUREG-0578 and in the October 30, 1979 letter from Harold R. Denton to All Operating Nuclear Power Plants.
Although the subcooling meter may be one of the indications that the shift technical advisor would monitor in his duties, it should not be the sole source of STA information. Additionally, the NRC staff would anticipate that the shift oper tors and shift supervisor would monitor the subcooling meter as a part of their monitoring of the plant status.
The October 30, 1979 NRC letter discusses the engineering training required if the shift technical advisor does not have a bachelor degree.
2.
SECTION 2.1.4 - Containment Isolation Provisions APC should provide information to demonstrate that resetting of any containment isolation signal generated by safety injection or manual initiation will not reopen isolation valves.
3.
SECTION 2.1.5c - Recombiner Procedures APC should review and uograde, as necessary, those criteria and procedures dealing with recombiner use.
4.
SECTION 2.1.5.b - Design Review of Plant Shielding The NRC source term (unmodified) should be used in the design review.
By January 1,1981 shielding modifications, if necessary, should be made to permit coping with a major accident, not merely for shutdown, despite existing constraints.
5.
SECTION 2.1.8.5 - Increased Range of Radiation Monitors The adequacy of effluent estimated based on grab samples is questionable; provisions should be made for estimating noble gar releases based on readings of monitoring instruments. Also, there is evidence that instruments meeting the NRC staff requirements are available for measuring effluents.
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6.
SECTION 2.1.8c - Improved Iodine Instrumentation Counting of the cartridges in the counting facility appears inadequate because of the time delay. APC should consider having single channel analyzers on the air samplers.
7.
Containment Water Level Monitor APC should provide the range of the currently installed wide range containment water level detectors. The NRC considers a range of monitoring at least 600,000 gallons acceptable.
8.
Containment Hydrogen Indication APC should provide the range of the currently installed containment hydrogen monitors. NRC considers a 0-10% range acceptable.
9.
SECTION 2.2.2.B - Onsite Technical Succort Center The APC response to this section of NUREG 0578 should address the number of people that can occupy the temporary cnsite technical support center.
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tuQ9, i kworuc Novembe 9
Meeting Summary for Alabama Power Company iles Local POR ORbl Reading
'fGR Reading H. Denton Ruble A. Thomas, Vice President E. Case Southern Services, Inc.
D. Eisenhut Post Office Box 2625 R. Tecesco Bimingham, Alabama 3 202 G. Zecn B. Grimes George F. Treworidge, Escuire W. Gammill Shaw, Pittman, Potts and Trewbridge L. Shao 1800 M Street, N.W.
J. Miller Washington, D. C.
20036 R. Vollmer T. J. Carter John Bingham,. squire A. Schwencer Sa1ch, Singham, Saker, Hawthorne, llams and Wa M D. Ziemann o00 North 18th Street E. C c 3f mingham, Alabama 35202 g,
ns
- g. Crutchfield Edward H. Keiler, Esqui re
- o. ur1mes Keiler and Suckley T. Ippolita 9047 Jefferson Hignway R. Reid River Ridge, Louisiana 70123 V. Noonan G. Knighton George S. Houston Memorial Librar~v D. Brinkman 212 W. Surdeshaw Street Project Manager Dothan, Alabama 36303 OELD 01&E (3)
C. Parrish/P. Kreutzer ACRS (16) faC Participants NSIC TERA Licensee Short Service List 1468 348
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