IR 05000298/1981022
| ML20033C829 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/10/1981 |
| From: | Dubois D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20033C826 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.46, TASK-TM 50-298-81-22, IEB-80-25, NUDOCS 8112040352 | |
| Download: ML20033C829 (5) | |
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APPENDIX
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U.S. NUCLEAR REGULATORY COMMISSION
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0FFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No.
50-298/81-22
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Docket No. 50-298 License No. DPR-46
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Licensee:
Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 l
Facility Name: Cooper Nuclear Station Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska-
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Inspection conducted: October 1-31, 1981 I
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r Inspector:
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D. L. DuBois, Resident Reacfor Inspector Date j
Projects Section 1 Approved by:
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l T. F. Westerman, Chief, Projects Section 1 Date
Insoection Summary Inspection on October 1-31, 1981 (Report No. 50298/81-22)
Areas Inspected: Routine, announced inspection of operationcl safety verifi-
cation; monthly equipment surveillance and maintenance observations; plant design d
changes;-environmental media sampling: environmental air monitoring stations;
reactor scram review; follow up to bu.'.. ins, licensee events, previously identified items, TMI action plan requirements and independent inspection. This inspection involved 143 inspector hours on site by one NRC inspector.
Results: Within the areas inspected no violations or deviations were identified.
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DETAILS 1.
Persons Contacted
- L. Lessor, Plant Superintendent P. Thomason, Ass't. Plant Superintendent R. Creason, Operations Supervisor P. Borer, Engineering Supervisor V. Wolstenholm, QA Supervisor J. Sayer, C & HP Supervisor R. Brungardt, Surveillance Planner C. Goebel, Administration Supervisor H. Jantzen, I & C Supervisor D. Norvell, Electrical Foreman
- Indicates presence at exit meetings.
2.
Operational Safety Verification The NRC inspector observed control room operations, instrumentation, controls, reviewed applicable logs, and conducted discussions with control room operators. The inspector verified operability of:
'B' Residual Heat Removal System
'A' Core Spray System
'B' Core Spray System
- 1 Diesel Generator Standby Liquid Control System 4160 VAC Vital Electrical Distribution System The inspector reviewed tagout records, and verified proper return-to-service of affected components, verified that maintenance requests had been initiated for equipment discovered to be in need of maintenance, that the appropriate priority was assigned, and that maintenance was performed in a timely manner commensurate with the priority assigned.
Tours of accessible areas of the facility were conducted to observe normal security practices, plant and equipment conditions including cleanliness, radiological controls, fire suppression systems, emergency equipment, potential fire hazards, fluid leaks, excessive vibration and instrumentation adequacy.
These reviews and observations we a conducted to verify that facility operations were in conformance utn the requirements established in the Technical Specifications, 10 CFR and Administrative Procedures.
No violations or deviations were identified in these areas.
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Surveillance Observations t
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The inspector observed portions of Technical Specification required surveillance tests to verify that testing was performed in accordance with adequate procedures, test instrumentation was in calibration, Limiting Conditions for Operations were met, removal and subsequent restoration of affected components was accomplished, test results
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conformed with Technical Specification and procedure requirements,
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tests were reviewed by personnel other than the person directing the test, and any deficiencies identified during testing were properly
reviewed and resolved by appropriate management personnel.
The following tests were selected and observed:
6.2.2.3.2 HPCI Steamline Space Temperature Switches Functional Test l
6.4.8.5 TIP Ball Valve Exercising 6.4.8.14 REC Critical Header Fan Coil Units Operability Test
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t These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established in the
- Technical Specifications,10 CFR and Administrative Procedures.
No violations or deviations were identified in these areas.
4.
Maintenance Observations The inspector observed portions of the following maintenance activities:
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MDC 81-064-Drywell.SRV Supports MDC 81-065 Torus Intervals MDC 81-081 SW-M0-898 Re-Modification-
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- WIT 81-1591
'B' Reactor FW Pump Turbine WIT P1-1595
'A' Reactor FW Pump Turbine
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WIT 81-1806 - HPCI Turbine Inspection l
WIT 81-1893 - Drywell Snubbcr Inspection-WIT 81-1977 - RF-A0V-FCV-11AA (Startup Flow Control Valve)
- 1 Diesel Generator Annual Inspection
- 2 Diesel Generator Annual Inspection
- Minor Design Change
- Work Item Tracking The following Clearance Orders were independently verified for proper restoration to service of affected component (s):
,81-510, MSIVs & RVs81-522, 1A RHR Pump 81-528, #1 Diesel Generator Bkr.81-547, #1 Diesel Generator 81-557, 'A' SW Booster Pump i
81-573, #2 Diesel Generator t
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The following Clearance Orders were reviewed:
81-500 through 81-510 Included with the above were checks for availability of redundant equip-
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ment, adequate safety isolation and clearance, accomplishment of work in accordance with approved procedures and Technical Specification require-
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ments, verifhation that QC checks were performed as required, clean-11 ness contro h and health physics coverages were adequate.
No violations or deviations were identified in the above areas.
5.
Review of Plant Operations The inspector observed the collection of environmental media samples including feed ano forage. All environmental air monitoring stations were also inspected for correct installation and operation.
No violations or deviations were identified.
6.
Plant Scram -- Safety System Challenge The inspector reviewed records and interviewed plant' personnel concerning an unscheduled reactor scram, which occurred.on September 12, 1981, at 12:58 P.M.,
(Scram Report #81-3). The reactor was initially subcritical with control rods being inserted per normal shutdown procedures in preparation for an extended outage which was to. include main turbine LP rotors replacement.
Reactor water level was being controlled manually using FCV-11AA which, due to failure to respond properly, resulted in a rapid injection of
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relatively cool makeup water from the main condensate system, causing the reactor to go critical and shortly thereafter scram, due to intennediate range high flux level. All other systems functioned as designed.
Appropriate corrective action was taken and the facility remained shutdown for the scheduled outage.
Subsequent calculations of reactor period and reactivity addition were performed by plant staff and General Electric (Letter from GE to NPPD, dated September 30,1981), which verified that reactor period and reactivity addition values remained within Technical
Specification limits. No unreviewed safety questions were discovered.
l FCV-11AA was repaired during the outage period.
7.
IE Bulletin Follow-up 80-25 (Closed) Operating Problems with Target Rock Safety-Relief Valves at BWRs NPPD letters dated February 13, 1981, and September 4, 1981, provide adequate response to the three items addressed in IEB 80-25:
Item 1:
During the SPing 1981 refueling outage (April 22 - June 7,1981)
the licensee disassembled and inspected all safety-relief valves, including the spare, for excessive Loctite.
Following. reassembly each actuator solenoid was functionally tested to insure operability.
Item 2: The inspector verified that CNS Operating Procedure 6.3.2.1, ADS Manual Valve Actuation (Rev. 10), dated February 20, 1981, meets the criteria
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for requiring inspection and testing of safety-relief valves found not to be functioning as designed.
Item 3: Closed in Inspection Report 81-10.
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8.
Licensee Event Follow-up The following LERs are closed on the basis of the inspector's in-office review, review of licensee documentation, and discussions with licensee personnel:
LER 81-02 LER 81-03 LER 81-06 9.
Follow up of Previously Identified Items (Closed) Violation 8102-01 (Inspection Report 81-02, paragraph 2):
Failure to Follow Procedure 1.6 When Tagging Out lo RHR SW Booster Pump The NRC inspector verified that the licensee completed all commitments discussed in their response dated March 26, 1981, and also determined that response to be adequate.
10.
NUREG - 0737 Clarification of TMI Action Pl,an Inspection Requirements Item II.K.3.46 (Closed) Michelson Concerns The NRC inspector verified licensee actions with regard to this item, based upon NPPD letter to NRR dated December 30, 1980, and NRR letter to NPPD dated July 14, 1981.
11.
Exit Meetings Exit meetings were conducted at tha conclusion of each portion of the inspection. The Plant Superintenuant was informed of the above findings.
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