IR 05000213/1980005
| ML19331B696 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 06/30/1980 |
| From: | Keimig R, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19331B690 | List: |
| References | |
| 50-213-80-05, 50-213-80-5, NUDOCS 8008120605 | |
| Download: ML19331B696 (4) | |
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U. S. NUCLEAR REGULATORY COMNISSION OFEICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-213/80-05 Docket No.
50-213 License No.
DPR-61 Priority Category C
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Licensee:
Connecticut Yankee Atomic Power Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name:
Haddam Neck Plant Inspection At:
Haddam, Connecticut Inspection Conduc d:
March 31 - April 4, 1980 Inspectors:
dthth 6/J7!80 1. H. 521th, Heactor inspector date date Approved by:
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J. R. Kelmi Chief actor Projects Section date
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No. 1, R S Bra Inspection Summary:
Inspection on Marcn 31 - April 4, 1980 (Report Number 50-213/80-05)
Areas inspected:
Routine, unannounced inspection by one regionally based in-l spector (20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />) which included:
participation in meetings between the licenseeandNRRpersonnelonthesubjectofemergencyplanning;planttours; and, followup of a plant trip which occurred on March 27, 1980.
Results:
No items of noncompliance were identified.
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Region I Form 12 (Rev. Apri 9 )20605 9 1
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DETAILS 1.
Persons Attending Meetings Connecticut Yankee Atomic Power Company H. Clow, Health Physics Supervisor
- J. Ferguson, Station Services Superintendent S. Fleming, Training Supervisor
- R. Graves, Station Superintendent A. Nericcio, Plant Public Affairs H. Wong, Engineer Northeast Utilities Service Company R. Brisco Radiological Protection Scientist R.Crandall,RadiologicalAssessmentEngineer E. Molloy, Engineer R. Rodgers, Chief, Radiological Assessment Branch Nuclear Regulatory Commission R. Caruso, NRR T. Jackson, Reactor Inspector T. McKenna, NRR
denotes those present at the ex.t interview conducted on April 3, 1980 In addition to the above personnel, the emergency planning meetings were attended by representatives of several state agencies, representatives of l
the Federal Emergency Management Agency, personnel under contract to the NRC and members of the public.
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All listed personnel did not necessarily attend all meetings.
2.
Emergency Planning Meetings Summary On April 1-3, 1980, a series of meetings was held to review and discuss the revised emergeicy plan for the Haddam Neck Plant.
The following meetings were held:
Tuesday, April 1, 1980 A fact finding and data collection tour of 1:00 p.m. - 5:00 p.m.
the plant was conducted and the following areas were reviewed:
(1)overviewofsite concept of emergency operations, (2) tour of site emergency facilities, (3) emergency action level instrumentation, (4) dose pro-jectionmethods,and(5) communications.
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Wednesday, April 2, 1980 NRR representatives met with the licensee to 1:30 p.m. - 5:00 p.m.
discuss NRC requirements and the results of and preliminary emergency plan reviews.
These Thursday, April 3, 1980 were technical meetings which were open for 9:30 a.m. - 12:00 p.m.
public observation but not public participa-tion.
Thursday, April 3, 1980 An open discussion was held with members of the 7:00 p.m. - 10:30 p.m.
public to determine their views on the state of emergency preparedness in the area.
The licensee's draft emergency plan, dated January 1980, was reviewed against NUREG 0654 requirements which were also published in January 1980.
As a result of the NRC review and this series of meetings, the licensee has committed to review the plan based on the new criteria and resubmit an updated plan, if required.
3.
Review of Plant Trip The inspector reviewed the licensee's investigation and assessment of the plant trip whica ace:cred on March 27, 1980.
The trip from 100% power was the result of a spurious containment isolation signal caused by the installation of a relay, in which contacts were in an incorrect configura-tion, in the containment isolation circuitry.
The following is a brief sequence of events:
March 27, 1422 hrs: High centainment pressure signal causes:
(1) con-tainmentisolation(3)reactortrip,and(4) turbine (2) Emergen (ECCS) actuation, trip.
Operators verified proper automatic equipment functions and took actions as specified in emergency procedures.
All reactor coolant pumps were tripped due to loss of
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component cooling water when containment isolation oc-I curred.
l After verifying no loss of reactor coolant, ECCS equip-ment was secured.
Reactor coolant pum Plant in normal hot March 27, 1443 hrs: shutdown condition.ps restarted.
March 28, 0144 hrs: Reactor taken critical.
March 28, 0402 hrs: Plant phased onto grid.
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Prior to returning to power the Plant Operations Review Committee met and reviewed the event.
It was determined that the procedure being used to make the modification to the containment isolation circuitry contained insufficient guidance to prevent the containment isolation signal which resulted.
The modification was completed while the plant was in hot standby.
All plant equipment operated as designed.
Noitemsofnoncompliancewereidentifiedintheinspector'sreviewof this event and the subsequent actions taken by licensee personne,1.
4.
Exit Interview The inspector met with licensee representatives (see Detail 1 for attendees)
at the conclusion of the inspection on April 3, 1980.
The inspector summarized the scene and findings of the inspection at that time.
Matters pertaining to emergency planning were covered during the meetings between NRC/NRR and the licensee.
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