ML19256F666
| ML19256F666 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/03/1979 |
| From: | Silver R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912190782 | |
| Download: ML19256F666 (7) | |
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UNITED STATES y ) >.-
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WASHINGTON, D. C. 20555 S
December 3,1979
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Docket No. 50-213 cICENSEE: Connecticut Yankee Atomic Power Company FACILITY: Haddam Neck Plant
SUBJECT:
SUMMARY
OF NOVEMBER 19, 1979 PHONE CONVERSATION REGARDING LESSONS LEARNED IMPLEMENTATION During a phone conversation on November 19, 1979, the NRC Lessons Learned Implementation Team discussed with the licensee its October 18, 1979 response to our September 13, 1979 letter.
The team infomed 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 commitment 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 Detection of Inadequate Core Cooling)
(Procedures Only), 2.1.7.a (AFW Initiation), 2.1.7.b (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.
By letter dated October 30, 1979, we provided additional clarification of the lessons learned requirements to all licensees. We also requested that within 15 days licensees justify proposed actions not in complete agreement with the staff's requirements and improve the implementation schedule where it differed from the staff's requirements. During this phone conversation we infomed the 1627 332 7012190782-
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/ licensee that those items listed in Enclosures 1 and 2 should be addressed in their response.
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, but no later than January 1,1980.
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\\e Richard D. Silver, Project Manager Operating Reactors Branch #2 Division of Operating Reactors Enclosures (3):
As Stated cc w/ enclosures:
See next page 1627 333 s
, cc w/ enclosures:
Day, Berry & Howard U. S. Environmental Protection Counselors at Law Agency One Constitution Plaza Region I Of fice Hartford, Connecticut 06103 ATTN:
EIS COORDINATOR JFK Federal Building Superintendent Boston, Massachusetts 02203 Haddam Neck Plant RFD el Mr. W. G. Counsil, Vice President Post Of fice Box 127E Nuclear Engineering and Operations East Hampton, Connecticut 06424 Connecticut Yankee Atomic Power Company Post Office Box 270 Mr. James R. Himmelwright Hartford, Connecticut 06101 Northeast Utilities Service Company P. O. Box 270 Hartford, Connecticut 06101 Russell Library 119 Broad Street Middletown, Connecticut 06457 Board of Selectmen Town Hall Haddam, Connecticut 06103 Connecticut Energy Agency ATTN:
Assistant Director Research and Policy Development Department of Planning and Energy Policy 20 Grand Street Hartford, Connecticut 06106 Director, Technical Assessment Division Office of Radiation Programs (AW-459; U. S. Environmental Protection Agency Crystal Mall !?.
Arlington, Virginia 20460 1627 334 s
ENCLOSURE 1 HADDAM NECK PLANT ITEMS THAT 00 NOT MEET SCHEDULE 1.
Section 2.1.3.a - Direct 'ndication of Valve Position You should note that the completion of the installation of this device is required by January 1, 1980.
2.
Section 2.1.3.b - Instrumentation for Detection of Inadeauate Core Cooling You are reminded of the Lessons Learned schedule requirement of January 1,1980 for completion of this item.
3.
Section 2.1.6.b - Shielding Review The design review and problem identification phase should be canpleted by January 1, 1980.
The modifications should be implenented by January 1,1981 (Category b).
Decisions about delay to SEP will be made after completion of the initial review.
4.
Section 2.1.8.a - Post-Accident Sampling The design review, procedure development and modification iden*.ification must be completed by January 1,1980.
The modifications should be implemented by January 1,1981 (Category B).
5.
Section 2.1.8.b - High Range Radiation Monitors The completion dates, January 1,1980 and January 1,1981, are requirements and should be met.
6.
Section 2.1.8.c - Improved Radiciodine Instrumentation The completion date, January 1,1980, is a requirement and should be met.
7.
Section 2.2.2.b - Onsite Technical Support Center You are reminded of the Lessons Learned Implementation schedule of January 1,1980 for completion of the tenporary onsite technical support center.
8.
Section 2.1.6.a - Systems Integrity You are reminded of the required canpletion date for the leak reduction program and for the establishment of the preventative maintenance program of January 1,1980.
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ENCLOSURE 1
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Section 2.1.4 - Containment Isolation a.
Modifications required to provide diversity in the containment isolation should be completed by January 1,1980.
b.
With regard to the requirement that all non-essential systems be automatically isolated, the extent of the modifications required will determine if this subject is appropriate for inclusion in the SEP.
10.
Containment Pressure, Containment Water Level, Containment Hydrogen Monitor The instrumentation required to monitor containment pressure, water level, and hydrogen concentration should be installed by the required date of January 1, 1981.
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ENCLOSURE 2 HADDAM NECK PLANT PROPOSED ACTION DOES NOT APPEAR TO COMPLY WITH LESSONS LEARNED REQUIREMENTS 1.
Section 2.2.1.b - Shift Technical Advisor Haddam Neck's proposal is for an on-call shift Technical Advisor to be supplemented in the longer-term by additional technical Lupport in the event of an energency.
The staff position is that an on-site Technical Advisor should be provided so that he is available in the control room within 10 minutes to provide the overview and accident analysis function.
The staff believes that this function is very important at the start of an event because this is the time that the shift supervisor must direct most of his efforts to response to the many plant alarms and to directing the reactor operators' actions. The staff fully supports the intent to provide additional technical support from off-site in the event of an energency. The requirement for the establishment of an On-Site Technical Support Center is intended to enhance this capability.
This does not alleviate the necessity to provide additional technical support at the beginning of an event when the shift supervisor and reactor operators may not have adequate time to perform this function.
The staff oosition is reiterated in the October 30, 1979 Harold R. Denton letter to All Operating Nuclear Power Plants.
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ENCLOSURE 3 HADDAM NECK PLANT CLARIFICATION OF LICENSEE'S POSITION IS NFEDED TO VERIFY C0f1PLIANCE 1.
Section 2.1.1 - Emergency Power Supply Requirtments for Pressurizer HTRS, Power-0rerated Relief Valves and Block Valves, and Pressurizer Level Indicators in PWRs Your response to this section did not address the specifics of the subparts of the position as described in NUREG-0578. Clarification is required.
2.
Section '.l.6.a - Systems Integrity c
By January 1,1980, CYAPCo is expected to provide a summary program description including leak rate measurements.
3.
Section 2.1.8.a - Post-Accident Samoling The sample analysis capability should include determination of H 2
concentration in the containnent atmosphere and detennination of dissolved gases in the primary coolant.
4.
Section 2.2.2.8 - Onsite Technical Support Center Address tne requirenent of Radiation Monitoring for the Onsite Technical Support Center as identified under clarification letter of October 30, 1979.
5.
Section 2.2.2.C - Onsite Ooerational Supoort Center Clarification is required in that you are requested to address the specifics of the position as described in NUREG-0578.
6.
Section 2.1.4 - Containment Isolation Provisions Information will be required to determine that resetting the containment isolation signal does not result in the automatic reopening of containment isolation valves.
7.
Section 2.1.5.a - Dedicated H Control Penetrations g
Further information will be required to demonstrate that a manual locked close valve meets the requirenent for dedicated hydrogen control penetrations.
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