IR 05000213/1978027
| ML19261B214 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/01/1978 |
| From: | Keimig R, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19261B190 | List: |
| References | |
| 50-213-78-27, NUDOCS 7902140183 | |
| Download: ML19261B214 (11) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-213/78-27 Docket No. 50-213 License No. DPR-61 Priority
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Category C
Licensee:
Connecticut Yankee Atomic Power Campany P. O. Box 270 Hartford, Connecticut 06101 Fccility Name:
Haddam Neck Plant Inspection at:
Haddam, Connecticut Inspection condu tpd:
ov 'ber 13-16,1978 M-/-
Inspectors:
/ /,
> tcc m cm Y.
J.' Lazarus, Reactor spector date signed date signed date signed Approved by:
A e
/2- / - 78
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Reactor Projects date signed
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Se No. 1 0&NS Branch Inspection Summary:
Inspection on November 13-16, 1978 (Report No. 50-213/78-27)
Areas Insoected:
Routine, unannounced inspection by a regional based inspector of plant operations including:
shift logs and operating records; tour of accessible areas; followup on licensee actions concerning selected IE Circulars; selected Licensee Event Reports; previous inspection findings; and, review of monthly operating reports. The inspection involved 24 inspector-hours on site by one regional based NRC inspector.
Results: Of the five areas inspected, one item of noncompliance was identified in one area (infraction - failure to provide an adequate locked barrier for high radiation areas).
790214o 6 3 Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted
- N. Burnett, Operations Supervisor
- H. Clow, Health Physics Supervisor R. Eppinger, Reactor Engineer J. Ferguson, Engineering Supervisor S. Fleming, Training Supervisor
- R. Graves, Plant Superintendent J. Kangley, Chemistry Supervisor
- R. Traggio, Assistant Plant Superintendent The inspector also interviewed other plant personnel including shift operations, engineering staff, and administrative personnel.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findinas (Closed) Unresolved Item (213/78-24-01): Qualification requirements for HP Supervisor as delineated in procedure ADM 1.1-1 are not con-sistent with Technical Specifications (TS).
Procedure ADM 1.1-1 has been revised and now reflects the TS qualification requirements.
3.
Shift Logs and Operating Records a.
The inspector reviewed the following plant procedures to deter-mine the licensee's established administrative requirements in this area in preparation for a review of selected logs and records.
ADM 1.1-5, Control Room Operating Log, Original.
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ADM 1.1-6, Plant Records Collection, Storage, Maintenance, and Disposition, Revision 4.
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ADM 1.1-43, Control Room Area Limits for Control Operators, Original.
ADM 1.1-44, Shift Relief and Turnover, Original.
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QA 1.2-2.4, Housekeeping Requirements, Revision 4.
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SUR 5.1-102, Monthly Audit of Bypass and Jumper Log, Revision 1.
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QA 1.2-14.1, Bypass and Jumper Control, Revision 1, March 26, 1975.
QA 1.2-14.2, Equipment Control (Locking and Tagging),
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Revision 1, January 1, 1976.
QA 1.2-16.1, Plant Information Reports, Revision 4.
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The inspector verified that these administrative controls were acceptable.
b.
Shift logs and operating records were reviewed to verify that:
Control Room log sheet entries are filled out and initialed;
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Auxiliary log sheets are filled out and initialed;
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Shift Supervisor and Control Room log entries involving
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abnormal conditions provide sufficient detail to communi-cate equipment status, lockout status, correction, and restoration;
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Log Book reviews are being conducted by the staff; Operating orders do not conflict with Technical Specifi-
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cation requirements;
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Jumper (Bypass) log does not contain bypassing discrepancies with Technical Specification requirements;
" Plant Information Reports" confirm there are no violations
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of Technical Specification reporting or LC0 requirements; and, Logs and records were maintained in accordance with
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Technical Specifications and the procedures in 5.a abov.
c.
The review included discussions with licensee personnel and the following plant shift logs and operating records.
NOP 2.2-2, Log Sheets which consist of Control Room
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Part 1 and Part 2, Primary Side Surveillance Form, Secondary Side Surveillance Form, and Radiation Monitoring Syrtem Daily Log for the period of October 1 through October 30, 1978.
Control Room Log Book for the period October 1 through
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November 15, 1978.
Night Orders Book for the period September 15 through
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November 12, 1978.
Bypass and Jumper Control Log for the period September 15
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through November 15, 1978.
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Tagging Log for the period September 14 through November 15, 1978.
Plant Information Reports (PIR) (PIR 78-85 through 78-108).
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PORC Minutes 78-50 through 78-60.
No items of noncompliance were identified.
4.
Plant Tour The inspector conducted an inspection tour of accessible areas of the plant, including the Primary Auxiliary Building, Turbine Building, Spent Fuel Building, Containment, Switch Gear Room, Diesel Generator Rooms, HP Control Point, Cable Spreading Area, and yard areas.
Part of this tour was conducted shortly after the inspector's arrival on site during the second shift on November 13, 1978.
Details and findings are :ioted belo a.
Monitoring Instrumentation and Annunciators Control Board monitoring instrumentation for power range nuclear instrument channels, pressurizer pressure and level, main coolant system average temperature, delta T, and inlet temperature, refueling water storage tank level, axial tiux offset, contial rod position, and radiation process monitors were obsened and compared with Technical Specification re-quirments several times during the inspection.
Control Board annunciators were observed for abnormal alarms each time the inspector was in the Control Rcom.
No itr.ms of noncompliance were identified and the reason for each existing alarm was satisfactorily resolved.
b.
Radiation Controls Radiation Controls established by the licensee, including posting and controls established for radiation /high radiation areas, radiological surveys, condition of step-off pads, and the disposal of protective clothing were observed for con-formance with the requirements of 10 CFR 20 and Technical Specifications.
Except as noted below, no items of noncompliance were identified.
During an inspection of the Residual Heat Removal (RHR) Pit in the Primary Auxiliary Building on Novemoer 15,1978, the inspector identified radiation levels in excess of 2,200 mrem /hr at one location on the grating level. A subsequent review of the licensee's radiological survey records for the charging and metering pump cubicles, done on November 14, 1978, indicated radiation levels in these areas were also in excus of 1000 mrem /hr.
The licensee had identified this increase in radiation levels through routine surveys and attributed the increases to increased fission product activity in the primary coolant.
Technical Specification 6.13.1 states in part that, for high radiation areas in which the intensity of radiation is greater than 1000 mrem /hr,
"...In addition, locked doors shall be provided to prevent unauthorized entry into such areas...."
The licensee in an attempt to meet this requirement had padlocked the short gates which are installed
at the entrance to each of the areas in question. The inspector indicated to the licensee that these locked gates are not a sufficient deterrent and cannot be considered as ".. locked doors...to prevent unauthorized entry....," as it is simple to climb over or otherwise bypass these gates. This represents an infraction level item of noncompliance (213/78-27-01).
c.
Plant Housekeeping Plant housekeeping conditions, including general cleanliness and storage of materials to prevent fire hazards, were observed in all areas toured to verify conformance with QA 1.2-2.4,
" Housekeeping Requirements." No fire hazards were identified and general cleanliness was act.eptable.
d.
Fluid Leaks and Piping Vibration Systems and equipment in all arcas toured were observed for the existence of fluid leaks and abnormal piping vibration.
No abnormal conditions were identified.
e.
Pipe Hangers /Sei".ic Restraints Spring pipe hangers and hydraulic shock suppressors installed on various piping systems throughout the plant were observed for proper installation, orientation, position, and fluid levels as applicable.
Nr discrepancies were identified.
f.
Emergency Power Availability The inspector verified that the four 480-volt buses were energized, both diesel generators were lined up for automatic actuation, off site power was available, and emergency batteries were operable by checking switch lineups and indications in the Control Room, Diesel Generator Rooms, and Switch Gear Room.
No items of noncompliance were identifie g.
Equipment Caution Tags / Jumpers The inspector verified that the following tags associated with maintenance on an RHR pump were in place as indicated in the Tagout Log:
Clearance Nos. 864-1, 2, 3, 5, and 6.
The inspector also verified that all jumpers missing from the jumper cabinet in the Control Room were accounted for in the Jumper and Bypass Log.
No discrepancies were identified.
h.
Selected Valve Positions By observation during the plant tour, the inspector verified that the following valves and associated locking devices were in the position required by Technical Specification 3.6 to insure the operability of core cooling systems.
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RH-FCV-602(lockedclosed,airsupplyisolated)
RH-FCV-796 (open, air supply isolated)
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SI-FCV-875 (blocked and locked open)
No items of noncompliance were identified.
i.
Licensee Plant Tours The licensee's policy and practice regarding plant tours nave not changed since the previous inspection in this area.
No formal administrative regtirements exist to specify frequency of tours by plant staff; however, it remains policy to conduct frequent tours to observe housekeeping and plant conditions.
j.
Control Room Manning Controi Room manning was reviewed several times during the inspection to verify conformance with the requirerents of Technical Specifications, 10 CFR 50.54k, and ADM 1.1-43.
No items of noncompliance were identifie.
IE Circulars Licensee actions concerning the following IE Circulars were reviewed by the inspector to verify that the Circular was fomarded to appropriate onsite management, a review for applicability was performed, and corrective action, when necessary, was adequate.
IEC 78-05:
Inadvertent Safety Injection During Cooldown
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Evaluation documented:
CY Memo Burnett to Graves (undated).
IEC 78-13:
Inoperability of Multiple Service Water Pumps
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Evaluation documented:
CY Memo DeLaurence to Ferguson, September 12, 1978.
IEC 78-15:
Improperly Installed Tilting Disc Check Valves
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Evaluation documented:
CY Memo Levine to Graves, August 2, 1978.
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IEC 78-16:
Limitorque Valve Operators Evaluation documented:
Memo Levine to Graves, August 9, 1978.
No items of noncompliance were identified. Licensee reviews for applicability and evaluations were acceptable.
6.
In-Office Review of Licensee Event Reoorts (LER's)
The inspector reviewed LER's received in the RI office to verify that details of the event were clearly reported including the accuracy of the description of cause and adequacy of corrective action. The inspector a~ iso determined whether further information was required from the licensee, whether generic implications were indicated, and whethe:- the event warranted on site followup. The following LER's were reviewed.
78-07, Pinhole Leak in "B" Charging Pump Recirc Bypass Valve
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78-08, Body to Bonnet Leak in "B" Charging Pump Recirc Bypass Valve
78-09, Pinhole Leak in Pressurizer Spray Isolation Valve
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78-10, Qualification Test Failure of Containment Electrical Penetrations
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78-11, Feedwater Piping Shock Suppressor Uncoupled 78-12, "B" Charging Pump Gauge Line Leak
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78-13, Hole in MI Cable Sheath for No. 1 CAR Fan Motor 78-14, Unsatisfactory Leak Test on Containment Electrical
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78-15, Inoperability of No. 4 Steam Line Flow Channel 78-16, HPSI Pump 1A Cracked Shaft Sleeve and Wear Rings
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78-17, Pressurizer Spray Valve Control Circuit Malfunction
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78-18, Inoperability of Turbine Load Cutback Circuit 78-19, No. 2 Steam Line Flow Channel Inoperative
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78-20, Cncrging Flow / Recorder Selector Switch Failure
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ETS 78-05, Fish Impingement Overrun
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ETS 78-06, Circulating Water Discharge AT Greater Than
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8 F/hr ETS 78-07, Fish Impingement Overrun
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ETS 78-08, Circulating Water Discharge aT Greater Than
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8*F/hr
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ETS 78-09, Fish Impingement Overrun Except as noted below for those LER's selected for further review (denoted by *), the inspector had no further questions in this are.
7.
On Site Licensee Event Followup For those LER's selected for on site followup, the inspector verified that reporting equirements of Technical Specifications and Regulatory Guide 1.16 had been met, that appropriate corrective action had been taken, that the event had been reviewed by the licensee in accordance with plant administrative procedures, and that continued operation of the facility was conducted within Technical Specification limits.
The followup included discussions with licensee personnel, review of PORC meeting minutes, and review of Plant Information Reports (PIR).
Details of findings are noted below.
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78-09, Pinhole Leak in Pressurizer Spray Isolation Valve The inspector reviewed PIR 78-60 and the PORC evaluation documented in PORC Minutes 78-37 which agreed with the corrective actions taken.
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78-10, Qualification Test Failure of Containment Electrical Penetrations
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78-13, Hole in MI Cable Penetration Sheath Review of the licensee's actions regarding modifications to electrical penetrations is documented in RI inspection report 50-213/78-17.
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78-11, Feedwater Piping Shock Suppressor Uncoupled The inspector reviewed PIR 78-67 and PORC Minutes 78-39 which further documented the licensee's evaluation and corrective actions. A tour of the containment on September 14, 1978 (RI Inspection Report 50-213/78-24) confirmed the operability of the feedwater shock suppressors.
78-15, Inoperability of No. 4 Steam Line Flow Channel
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The inspector reviewed PIR 78-72, PORC Minutes 78-44, and the Shift Supervisor's Log to verify that a plant shutdown was promptly commenced and not terminated until a jumper was installed to trip the failed channe.
78-18, Inoperability of Turbine Load Cutback Circuit
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The inspector verified that the plant startup procedure had been revised to include steps to insure that the pressure switch isolation valve is opened prior to startup.
No items of noncompliance were identified in this area.
8.
Review of Reactor Coolant System (RCS) Radiochemistry Records The inspector reviewed RCS radiochemistry log sheets (surveillance test SUR 5.4-16) to verify that total specific activity for the period January - October 1978 was kept within the limits of Technical Specification 3.2.
No instances of noncompliance were identified.
9.
In-Office Review of Monthly Operatino Reports The inspector reviewed the licensee's Monthly Operating Reports for August - October 1978 in the RI Office to verify that reporting requirements were met.
No inadequacies were identified.
10.
Exit Interview The inspector held a management meeting at the conclusion of the inspection on November 16, 1978 (see paragraph 1 for attendees)
to discuss the scope and findings of the inspection as detailed in this report.