IR 05000029/1979006
| ML19254E506 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 09/14/1979 |
| From: | Keimig R, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254E500 | List: |
| References | |
| 50-029-79-06, 50-29-79-6, NUDOCS 7911010404 | |
| Download: ML19254E506 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
79-06 Docket No.
50-29 License No.
DPli-3 Priority Category C
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Licensee:
Yankee Atomic Electric Company 20 Turnpike Road Westborough, Massachusetts Facility Name:
Yankee Nuclear Power Station (Yankee-Rowe)
Inspection At:
Rowe, Massachusetts Inspection Conducted: _ June 26-28, 1979 Inspectors:
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W. J.
arus p actor Inspector
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date date
[ Y!77 Approved y:
A. R. Kefm% Chief, Reactor Projects
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Section No. 1, RO&NS Branch
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Inspection Summary:
Inspection on June 26-28, 1979 (Report No. 50-29/79-06)
Areas Inspected:
Routine unannounced inspection of plant operations; follow-up on selected Licensee Event Reports (LER's); and followup on selected IE Bulletins.
The inspection involved 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> on site by an NRC regional based inspector.
Results:
No items of noncomp ice wert identified.
1281 005 Region I Form 167
'l911010 bf (August 1979)
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DETAILS 1.
Persons Contacted
- H. Autio, Plant Superintendent T. Danek, Operations Supervisor R. Durfey, Technical Assistant
- P. Laird, Maintenance Supervisor
- J. Staub, Technical Assistant to the Plant Superintendent
- N. St. Laurent, Assitant Plant Superintendent The inspector also interviewed other licensee employees, including opera-tors and members of technical and administrative staff.
- Denotes those present at exit interview.
2.
Review of Plant Operations The inspector observed plant operations from the Control Room (plant at full power) and verifed that no abnormal alarms existed and that required engineered safety feature systems were properly aligned for automatic actuation based on switch lineups and valve position indication on control boards.
The inspector conducted a tour of other acussible areas of the plant,
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including the Primary Auxiliary Building, Turbine Building, Safety Injec-tion Building, Switch Gear Room, Diesel Generator Rooms, Radweste Build-ing, and HP Control Point Area to determine the status of radiation pro-tection controls, housekeeping and cleanliness, exis+ence of fl id leaks and abnormal piping vibration.
No items of noncompliance or abnormal conditions were identified.
3.
In-Office Review of Licensee Event Reports (LER's)
The inspector reviewed LER's received in the RT office to verify that details of the events were clearly reported including the accuracy of the description of cause and adequacy of corrective action.
The inspec-tar also determined whether further information was required from the licensee, whether generic implications were indicated, and whether the event warranted on-site followup.
The following LER's were reviewed:
79-12, SI Accumulator Time Delay Relay Setpo:nt Drift
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79-13, SI Accumulator Cover Pressure Greater Than 15 Psig
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79-14, CA-V-688 Failed Leak Rate Test
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The inspector had no further questions on these LER's.
4.
IE Bulletins Licensee action concerning the following IE Bulletins was reviewed by the inspector to verify that:
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The Bulletin was forwarded to appropriate onsite management; A review for applicability was performed;
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Information submitted in the licensee's response was accurate; and,
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Correction action (if required) was adequate.
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IEB79-02,PipeSuppoNBasePlatesaithConcreteExpansionAnchor
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Bolts In a letter dated March 20, 1979, the licensee requested that a full responce to this Bulletin be deferred until the seismic design basis for the plant is established under the Systematic Evaluation Program.
The inspector stated that in light of the issuance of IEB 79-02 Revision 1 on June 21, 1979, that this was not acceptable, and that
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as required in this revision, they must respond to demonstrate that anchors of this type are performing /or will perform design require-ments, even if they are not for seismic purposes.
This includes sup-ports in safety related systems which are dead weight support or rest.'cints for operational transients.
The licensee acknowledged this and agreed that these issues would be addressed in an additional response letter.
Fuether followup in this area will be performed during subsequent inspections.
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IEB 79-04, Incorrect Weights 'ar Velan Check Valves The inspector reviewed a document from the supplier of the Velan valves in use at Yalkee-Rosie (TWX 710-390-0739) which certifies tiiut plant drawing P2-8993 indicates the correct weights for the valves supplied.
The inspector had no further questions in this area.
IEB 79-06A, Three Mi % Island Incident
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In a review of licensee responses to this Bulletin, dated April 26, May 16, 24, and June 20, the inspector identified the following five areas in which licensee actions / commitments are not in confor-mance with Bulletin requirements.
(1) Emergency procedures specify that operators maintain 200 psig system overpressure vs. the required 50 F subcooling.
1281 000
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(2) Prerequisites for securing charging pumps following safety injection (3I) initiation are not addressed.
(3) 20 minute minimum for o',eration of HPSI/LPSI systems following SI not addressed.
(4) Continued operation o-reactor coolant pumps following SI not as required.
(5) Responses did not identify specific parameters to be monitored by operators in evaluating plant conditions.
The inspector stated tiat these items must be addressed, and that any differences between Bulletin requirements and plant staff. posi-tion must be fully explained and justified in a further response to the Bulletin.
The licensee r 'nowledged this and agreed that a further response was necessar, ;o resolve these issues.
The inspec-tor will continue to followup in these areas during subsequent inspections.
IEB 79-09, GE Type AK-2 Circuit Brakers
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The inspector's review of plant drawings 9699-ESK-6A-5, 6B-4, and
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6C, verified that the UV trip devices which are supplied as an option with these circuit breakers, are not used in safety related
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systems at Yankee-Rowe.
The inspector had no further questions in this area.
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IEB 79-10, Requalification Training Program Statistics The inspector reviewed requalification examination summaries for 1975-1978 to verify that the statistics reported in the licensee's response of May 22, 1979 to the IEB were correct.
No discrepancies were identified.
5.
In-Office Review of Monthly Statistical Reports The inspector reviewed the licensee's Monthly Statistical Reports for the period April-May 1979 to verify that reporting requirements were being met.
No reporting inadequacies were identified.
6.
Exit Interview The inspector met with licensee representatives (see detail 1 for attend-ees) at the conclusion of the inspection to discuss the scope and findings of the inspection as detailed in this report.
1281 007