ML17318A460
| ML17318A460 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/21/1979 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912040176 | |
| Download: ML17318A460 (7) | |
Text
NOV 21 19I9
@()gij hajjjij,~( 8K t'ICENSEE:
Indiana and Michigan Power Company Docket No. 50-315 and 316 FACILITY:
Donald C. Cook, Nuclear Plants Units 1 and 2
SUBJECT:
SUMMARY
OF NOVEMBER 15, 1979',PHONE'..CONYERSATION REGARDING LESSONS LEARNED IttPLEMENTATION Buring a pho'ne conversation on November 15, 1979 the NRG L~essons 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 l.
P The team also informed the licensee of those items for which further clafification.
of,.the licensee's commitment is necessary to demonstrate compliance with the lessons learned requirements.
These items and the associated team questions are listed in Enclosure 2.
Items 2;.1.3.6 (Instrumentation for Detection of Inadequate Core Cooling)
(Procedures only), 2.1.7.a (AFW Initiation), 2/1/7/6 (AFW 'Flow), and 2..1.9 (Accident
, and Transient Analysis) were not.discussed since these items are being implemented by the Bulletins and Orders-Task Force.
I 0<igtnnl signed by Enclosure (2):
I AS Stated cc w/enclosures:
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Dave 'Wigginton, Project Manager Operating Reactors Branch Pl Division of Operatingt Reactors Igg,070
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November 21, 1979 Meeting Notice for Indiana and Michigan Power Company
<Oocket Files NRC PDR Local PDR ORBl Reading NRR Reading H; Denton E.
Case D. Eisenhut R. Tedesco B. 'Grimes R. Vollmer
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J. Hiller L. Shao W. Gammill G. Zech A. Schwencer
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Check
. G. Lainas D. Crutchfield B. Grimes T. J. Carter T. Ippolito R. Reid V. Noonan G. Knighton U. Brinkman P. T.
Kuo Project Manager
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K R; Fraley,'CRS TERA J.
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Buchanan Principal Staff Receptionist, B
Program Support reutzer (16)
Participants ethesda Branch Mr. Robert W. Jurgensen Chief Nuclear Engineer American Electric Power Service Corporation 2 Broadway New York, New York 10004 Gerald Charnoff, Esquire Shaw,"Pittman, Potts and Trowbridge 1800 'H Street, N.W.
Washington, D. C.
20036 Citizens for a Better Environment 59 East Van Buren Street Chicago, Illinois 60605 Maude Preston Palenske Memorial Library 500 Market Street St. Joseph; Michigan 49085 Mr. D. Shaller, Plant Manager Donald C.
Cook Nuclear Plant P. 0.
Box 458 Bridgman, Michigan 49106 Hr. Robert Masse Donald C.
Cook Nuclear Plant P. 0.
Box 458 Bridgman, Michigan 49106
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 21, 1979 Docket No. 50-315 and 316 LICENSEE:
Indiana and Michigan Power Company FACILITY:
Donald C. Cook, Nuclear Plants Units 1 and 2
SUBJECT:
SUMMARY
OF NOVEMBER 15, 1979 PHONE CONVERSATION REGARDING LESSONS LEARNED IMPLEMENTATION During a phone conversation on November 15, 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 also informed the licensee of those items for which further-clafification of the licensee's commitment is necessary to demonstrate compliance with the lessons learned requirements.
These items and the associated team questions are listed in Enclosure 2.
Items 2.1.3.6 (Instrumentation for Detection of Inadequate Core Cooling)
(Procedures only), 2.1.7.a (AFW Initiation), 2/1/7/6 (AFW Flow), and 2.1.9 (Accident and Transient Analysis) were not discussed since these items are being implemented by the Bulletins and Orders Task Force.
Enclosure (2):
As Stated Dave Wigginton, roject Manager Operating Reactors Branch ~l Division of Operating Reactors cc w/enclosures:
See next page
ENCLOSURE 1
ITEMS THAT DO NOT MEET LESSONS LEARNED IMPLEMENTATION SCHEDULE 1.
SECTION 2.1.3.a - Direct Valve Position Indication Guidance in the October 30, 1979 letter should be followed on implementation of this requirement by January 1,
1980 instead of the proposal to install during the first suitable outage.
2.
SECTION 2.1.3 (b)
Instrumentation for Inade uate Core Coolin Schedule for implementation of the subcooling meter is January 1,
1980.
The licensee states that the meter will be installed by April 1980.
Guidance in the October 30, 1979 letter should be followed with respect to subcooled meter requirements.
3.
SECTION 2.1.6.a -
S stem Inte rit for Hi h Radioactivit The January 1,
1980 deadline is a firm requirement.
By that time AEP should provide a summary description of its program and leak rate measurements.
The program should include testing.
4.
SECTION 2.1.8.a - Post-Accident Sam lin The design review, procedure development and modification identification must be completed by January 1, 1980 and the necessary modifications must be implemented by January 1,
1981.
ENCLOSURE 2
COOK 1/2 CLARIFICATION OF LICENSEE'S POSITION IS NEEDED TO VERIFY COMPLIANCE 1.
SECTION 2.1.1 - Pressurizer Heaters AEP's response to the issue of engineering pressurizer heaters did not address the part 2, 3 and 4 of this position.
Additional clarification which addresses these parts of the position will be required.
2.
SECTION 2.1.3 (a) - Direct indication of Valve Position PORVs have limit switches which give control room indications but are not alarmed.
The alarm on the temperature device is not sufficient.
Pressurizer safety values must also have positive indication and alarms.
3.
SECTION 2.1.8.a - Post-Accident Sam lin The sample analysis capability must include determination of hydrogen gas in the containment atmosphere as well as disolved gases (H, 02) in the reactor coolant.
If a meeting with the NRC staff on this subject is desired, AEP should formally request such a meeting.
The lessons learned team will investigate the need for an industry wide meeting on the generic subject.
4.
SECTION 2.1.8.c - Im roved Iodine Instrumentation The instrumentation should be shown to work in an environment of high concentrations of noble gases.
By January 1,
1981 capability should exist for flushing the cartridges with clean gas and for counting the cartiridges in a low background area.
5.
SECTION 2.2.1 (b) - Shift Technical advisor STA AEP states that the 'STA will be on caIl and at no time over 45 minutes from the plant.
The NRC nearterm position requires that the STA be on shift and available in the control room within 10 minutes.
6.
SECTION 2.2.2.B. - Technical Su ort Center Address the requirement of radiation monitoring for the onsite technical support center as-identified by, clarification letter of October'0',
1979.