IR 05000213/1981008
| ML20010C536 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/31/1981 |
| From: | Elsasser T, Tanya Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20010C533 | List: |
| References | |
| 50-213-81-08, 50-213-81-8, NUDOCS 8108200171 | |
| Download: ML20010C536 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Regi"1 I'
Report No.
50-213/81-08 Docket No.
50-212 License No.
DPR-61 Priority-Category C
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Licensee:
Cor.necticut Yankee Atomic Power Company P.O. Box 270 Hartford, Connecticut 06101 Facility Name:
Haddam Neck Plant Inspection at:
Haddam, Ccr.necticut
/ une 22 - July 24,1981 J
Inspection conduc e :
-Inspectors:
I tl0 7/.>7[8/
1.H. 3mitn, denior Kesident inspSCtor date' signed
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date signed o
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date signed 7/3//8/
Approved by:
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T.C. ElsasF, Chief, Reactor Projects date signed Section l V Division of Resident and Project Inspection Inspection Summary:
Inspection on June 22 - July 24, 1981 (Report No. 50-213/81-08)
Areas Inspected: Routine, unannounced inspection of plant operations including:
tours of the facility; log and record review; licensee action on previous inspection findings; Licensee Event Reports; and preparations for refueling.
The inspection involved 55 inspector-hours by the senior resident inspector.
Results: No items of noncompliarce were identified.
Region I Form 12 (Rev. April 77)
8108200171 stoso4'
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DETAILS h
Persons Contacted The below listed technical and supervisory personnel were among those-contacted:
G.H. Bouchard, Maintenance Supervisor T.W. Campbell, Instrument and Control Supercisor H.E. Clow, Health Physics Supervisor J.H. Ferguson, Station Services Superintendent R.L. Gracie, Operations Assistant R.H.i Graves, Station ' Superintendent G.R. Hallberg, Security Supervisor J.M. Levine, Operations Supervisor R.Z. Test, Eagineering Supervisor R.P. Traggio, Unit Superintendent Other licensee staff and operating personnel were also interviewed during the course of the inspection.
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Licensee Action on Previous Inspection Findings
'(Closed) Inspector Follow Item (213/80-08-08):
Review maximum radiation limits for ion exchangers ano demineralizers. The licensee does not use external contact radiation levels as a criterion for replacing ion exchanger resin. Resin is replaced based on the pressure drop across the resin bed and the decontamination factor of the resin bed.
Contact radiation levels of the in service letdown ion exchanger may be in excess of 1000 rem per hour, while radiation levels outside the ion exchanger shielded enclosure are generally only several millirem per hour. Additionally, the licensee has experienced no difficulty in meeting raatation limits when shipping spent resin for disposal.
Current licensee practices in this area are considered satisfactory.
(Closed) Inspector Follow Item (213/80-11-02):
Procedural revision to prevent possible radioac.lve gas release.
Procedure NOP 2.ll-1-C, ' Sampling System - Normal Operation", has been modified to
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include warning steps to alert personnel taking samples to the co,mquences of improper valve manipulation. Licensee action on this item is satisfactory.
(Closed). Inspector Follow Item (213/80-15-06):
The licensee changed procedure E0P 3.1-5-C, " Steam Generator Tube Failure",
and removed reference to steam generator power operated relief valves.
Licensee action on this item is satisfactory.
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(0 pen) Unresolved Items (213/80-18-06 and 80-18-07):
Incorporate ISI charging pump and service water pump performance curves into approved procedures.
Performance curves have not yet been incorporated into appropriate procedures. A licensee representative stated that the performance curves would be incorporated into appropriate procedures ty August 31, 1981.
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fadew of Plant Operation - Plant Tours _
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a.
During the course of the inspection, the inspector conducted multiple tours of the following plant areas:
-- Control Room
-- Primary Auxiliary Building
-- Vital Switchgear Room
-- Diesel Generator Rooms
-- Turbine Building
-- Intake Building
-- Control Point
-- Security Building
-- Yard Areas b.
The following observations / determinations were made:
-- Radiation protection controls.
Step-off pads, storage and disposal of protective clothing and control of high radiation areas were charved for adequacy in all areas toured. The inspector also rv jewed routine plant radiation survey sheets and current Radiation wrk Permits.
No unsatisfactory conditions were identified.
-- Monitoring instrumentation. The inspector verified that selected instruments were functioning properly and that the displayed parameters were within Technical Specification limits.
-- Control room annunciators.
Lighted annunciators were discussed with control room operators to verify that the reasons for them were understood and corrective action, if required, was being taken. On average, only one or two annunciators were lighted on each centrol room visit.
-- Valve positions. The inspector verified that selected valves were in a position or condition required by the Technical Specifications.
No unsatisfactory conditions were identi#ied.
-- Plant housekeeping.
Housekeeping was observed in all areas toured, including control of flamable material. No unsatisfactory conditions were identified.
-- Fluid leaks. All areas toured were examined for evidence of excessive fluid leaks. None were foun.
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- ; Piping vibrations. All areas toured were examined for evidence of-excessive piping vibration. None were indicated.
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- ! Control room manning. Thelinspector verified that control room-manning requirements of the Technical. Specifications were being met.
-- Security.
During theiinspection, observations were made;of p1 ant.
. security including adequacy of physical barriers,1 access. control, vehicle control. and searches. -No unacceptable conditions were identified.
Shift' Logs and Operating Records a., The inspector reviewed selected operating logs and records against the require;ner.ts of the following procedures:
-- ADM l'.1-5, C introl Room Operating Log;
-- QA'_1.2-14.1, Bypass and Jumper Control;
-- ADM-1.1-43, Control Room Area Limits' for. Controi 0;erators;
-- N0P 2.2-2, Steady State Operation and Surveillance;
-- ADM 1.1-44, Shift Relief and Turnover;
-- QA 1.2-2.4, Housekeeping Requirements;
-- QA 1.2-16.1, Plant Information Reports; and
-- QA 1.2-14.2, Equipment Control.
b.
Shift Logs and operating records were reviewed to verify that:
-- Control Room log sheet entries are filled out and initialed;
-- Auxiliary log sheets'are filled out and initialed;
-- Control Room Log entries involving abnormal conditions provide sufficient detail to consnunicate equipment status, lockout status, correction and restoration;
-- Operating Orders do not conflict with Technical Specifications;
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-- Plant Information Reports confirm there are no violations of.
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Technical Specification requirements; and
--. Logs and records are maintained in accordance with Technical
Specif; cations and the procedura noted above.
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c.
The following operating logs and records were reviewed:
-- N0P 2.2-2, Log sheets which consist of Control Room, Part 1 and 2, Primary Side Surveillance Form, Secondary Side Sui /eillance Form, and Radiation Monitoring System Daily Log;
-- Shift Turnover Sheets;
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-- Jumper Log;
-- Tag Log; and
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-- Control Room Operating Log.
d.
No unacceptable conditions were identified in this area.
Licensee Event Reports (LER's)
Through direct observations, discussions with licensee personnel, and review cf records, the following event reports were reviewed to determine that repoi'tability requirements of the Technical Specifications and Station Administrative and Operating Procedures were fulfilled, imediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished.
81-06 Auxiliary feedwater pump control valve diaphram failed. The failed diaphram was replaced.
81- 07 Diesel generator load sequence timer out of tolerance. The 20 second acceptance criteria for start of the charging pump was exceeded by 0.2 seconds. The timer was reset.
81-08 Auxiliary feedwater system valve lineup error.
Due to a procedural valve lineup sheet error, the "A" pump minimum flow recirculation valve was shut while isolating the "B" nump for maintenance. Under accident conditions the "A" pump would have functioned properly.
The "A" recirculation valve was repositioned and the procedure was corrected.
Review of Periodic and Special Reports
Upon receipt, periodic and special reports submitted by the licensee pursuant to Technical Specification 6.9.1 were reviewed by the inspector.
This review included the following considerations:
the report includes the information required to be reported by NRC requirements; planned corrective action is adequate for resolution of identified problems; determination whether any information in the report should be classified as an abnormal occurrence; and the validity of reported information.
Within the scope of the above: the follow'ng periodic reports wen reviewed by the i.upector:
-- Monthly Operating Report 81-6 for the month of June 198.....-
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L Preparation for Refueling a.
Scope The procedures and documentation related to the receipt, handling and inspection of new fuel assemblies for the upcoming refueling outage were reviewed. At the time of the inspection approximately 36 new fuel assemblies had been delivered.
A total of 54 assemblies will be delivered prior to the refueling outage.
b.
Documents Reviewed
-- SNM 1.4-1-C, "Recefpt and Removal of New Fuel from Carrier", dated March 27, 1981
-- SNM 1.4-2-C, " Removing New Fuel from Shipping Container s", dated February 15, 1980
-- SNM 1.4-3-C, "New Fuel Detail Inspection", dated March 27, 1981.
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Findings On several occasions, the inspector witnessed the removal of new fuel from the carrier, removal of new fuel from the shipping containers and detail inspection of new fuel. No discrepancies were identified.
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Surveillance and Maintenance Activities a.
Surveillance During a routine tour of the control room, the inspector witnessed SUR 5.1-23, " Routine Control Rod Motion Check", being conducted by two control room operators.
No unacceptable conditions were identified.
b.
Maintenance The inspector witnessed maintenance conducted in accordance with procedure M 8.2-21-C, " Maintenance on Reactor Control and Protection System Defeat Switch 1/PM 41X" The defeat switch is used to relay loop average tempera-
'ure and delta temperature signals to the three low pressure scram calcu-
.ators and to defeat the signal from the fourth loop. When the-loop one
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average temperature instrument failed, the licensee discovered that the switch was mechanically bound and could not be placed in the loop one position to defeat tne failed signal. The inspector verified that the maintenance was conducted using art approved procedure, that personnel were properly qualified and briefed, and that the minimum scram logic required by technical specifications was maintained.
No unac, actable conditions were identified.
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Exit interview At periodic intervals during the course of the inspection, meetings were held with senior licensee management personnel to discuss inspection scope and findings.
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