IR 05000483/1984049

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Insp Rept 50-483/84-49 on 841201-850315.No Violation or Deviation Noted.Major Areas Inspected:Observations of Plant Operations,Cancellation Commitments for Unit 2,10CFR50.55(e) & Part 21 Items
ML20205A207
Person / Time
Site: Callaway Ameren icon.png
Issue date: 04/04/1985
From: Forney W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20205A201 List:
References
50-483-84-49, NUDOCS 8504250454
Download: ML20205A207 (5)


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i U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-483/84049(DRP)

Docket No. 50-483 License No. NPF-30 Licensee: Union Electric Company Post Office Box 149 - Mail Code 400 St. Louis, MO 63166 Facility Name: Callaway Plant, Unit 1 Inspection At: Callaway Site, Steedman, MO 65077 Inspection Conducted: December 1, 1984 through March 15, 1985 Inst actor: J. H. Neisler Approved By:-

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Reactor Projects Section 1A Dafe Inspection Summray:

Inspection on December 1, 1984 through March 15, 1985 (Report No. 50-483/84049(DRP))

Areas Inspected: Routine, unannounced safety inspection of previously identi-fied items, 10 CFR 50.55(e) and 10 CFR 21 reportable items, observation of plant operations, and cancellation commitments for Unit The inspection involved a total of 120 inspector-hours by one NRC inspecto Results: No violations or deviations were identified during this inspectio PDR ADOCK 05000483 G PDR

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DETAILS Persons Con'tacted R. L. Powers, Assistant Manager QA

. *R. Veatch, Supervisory Engineer QA-J. Laux, Supervisory Engineer, QA C.-Plows, Consultant,-QA G.-Patrissi, Consultant, Fire Protection J. Patterson, Assistant Superintendent,' Operations G. Wilson,. Engineer (Daniel), QA

'W.;Reilly, SNUPPS

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Doyne, General Superintendent Nuclear Construction W..Norton, Engineer, QA LW. Weber, Manager Nuclear Construction J. : Baker, Construction Engineer

  • L. Kanuckel, Engineer, QA
  • R. Plautz, Engineer, QA

'* Denotes those present at the exit meetin . -Licensee Action Regarding Previously Reported Items (Closed) Open-Item-(50-483/84-15-01): This item was previously reviewed'in Inspection Report 84-41' At that time, the inspector stated that to close-

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.this item, the licensee must provide. documentation from Underwriter Labora-tories (UL) which indicates that UL has reviewed the data for the reworked check valves ~and that UL will retain the listing of'the reworked check-valve The Underwriters Laboratories letter dated September 26, 1984 on the reworked check valves has been reviewed by the licensee and copies have been forwarded to Region II This item is considered to be close (Closed) Open Item (50-483/84-15-02): Proposed Technical Specifications for remote shutdown panel does not consider all of the required instru-mentation for safe shutdown. NRC License No. NPF-30 was issued October 18, 1994, including Appendix A, Technical Specifications. NRR Division of Licensing determined that the instruments listed in the open item did not need to be included in Technical Specification 3.3.3.5, Table 4.3-6 to assure that the reactor could be shutdown and maintained in the required 4- hot shutdown condition from the remote control panel. The inspector has

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no further concarns in this area. This item is considered to be close (Closed) Open Item (50-483/84-41-02): Safe shutdown being achieved from the' remote shutdown panel in the event of a particular control room fir A postulated fire which could cause instantaneous fire damage to a circuit i (hot short) could cause loss of power and control to needed safe shutdown equipmen SNUPPS review of possible damage from'the instantaneous fire resulted in the licensee committing to install five new isolation switches

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and modifying four existing switches. As an interim measure the licensee

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has revised Off-Normal Operating Procedure OTO-ZZ-00001 to manually oper-ate safe shutdown switches or breakers at the local control. panels. The inspector verified that procedure OTO-ZZ-00001 has been revised to require .

the manual operation of these switches. This item is considered to be

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closed.

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_( Closed) Severity. Level IV Violation (483/81-14-03): Failure to witness.

. electrical test QCP-304 was revised to require all safety-related cable related cable _ tests to be witnessed by. quality inspectors. The inspec-tor's review indicated that cables tested and not witnessed by a quality

< -inspector were retested and the tests were witnessed in accordance with

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the revised procedure. This item is considered to be close ,(Closed) Severity Level V Violation (483/82-10-02): Minimum bend radius violation _during or. subsequent to cable installatio The inspector ascer-i .tained that craft personnel had been retrained in cable pulling and termi-nation with emphasis on bend radius specification Safety-related trays

. were walked down and deficiencies were corrected by the licensee. Addi-

- .tional walkdowns by the inspector subsequent to the licensee's corrective action showed cables to be in compliance with bend radius specification This item is considered to be close ' Review of Licensee Actions Regardina 10 CFR 50.55(e) and 10 CFR 21 Reportable Items i- (Closed) Construction Deficiency Report (50-483/84-11-EE): Improperly i rated field run cable used to connect Valcor and Target Rock solenote in Class 1E applications. This deficiency involved approximately 37 Valcor and 20 Target Rock Class 1E solenoid valves. Field rework to replace the 90' degree C field wiring ~with high temperature wiring wit.-.

200 degree C rated insulation has been completed on 34 of the Valcor valves ano on 10 of.the Target Rock Valves. The remaining valves are to be reworked during the first refueling outag The.. inspector observed

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i the rework on Valcor valves in the south pipe penetration room and veri-

[ fied that the higher rated cable was installe Review of work schedules

. indicated that the remaining valves are tracked for rework during the

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first refueling outag This item is considered to be closed.

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(Closed) Terry Corporation 10 CFR 21 Report (50-483/84-02-PP): Valve stem guide found loose on valve stem. This item was reported to the NRC in a letter from Terry Corporation dated April 9, 1984. The upper valve

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stem guide (P/N 090326A) was found loose on the valve stem preventing the

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governor valve from fully closing due to jamming between the inner and outer valve spring seats. This part was shipped to Callaway as an oper-ating spare part. The part was identified in the warehouse and rejected by quality contro .

The part was returned to the vendor-per MSR 850082 on January 24, 198 This item is considered to be closed.

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. Plant Operations The inspector observed activities relative to plant operations during the report period. The inspector was present when the plant attained-100% power. Observation of plant parameters indicated that all systems were functioning within design boundarie The inspector observed shift turnovers, routine operations, recoveries from plant trips, approach to criticality on three occasions, plant heat-up and ascension to full power operations. In each of the above activities, the operators' strict adherence to approved plant operating procedures demonstrated the adequacy to their training and their cap-abilities to operate the plant safel . Callaway Unit 2 The licensee requested in April 1982 that construction permit CPPR-140 for Callaway Unit 2 be rescinde Union Electric letter ULNRC-575, dated August 17, 1982, documented licensee commitments to perform certain acti-vities relative to the cancellation of the unit: Site development, excavation and backfill. The licensee committed to maintain the slopes of the excavation, to maintain the excava-tion's drainage system and to seed the slopes to preclude erosio Essential service water cooling tower foundatio The licensee's commitment is to cut off or bend over the reinforcing steel pro-jecting from the concrete foundation. Since the foundation is at or below grade level, the concrete is to remain in plac Other Unit 2 facilities such as buried piping and electrical duct banks that had been installed to avoid future excavations at the ultimate heat sink that might disrupt Unit 1 operations are to be abandoned in plac The inspector reviewed site development plans for work scheduled to be completed during the 1985 construction season. These plans show final grading of slopes, installation of permanent wiring to the excavations de-watering pumps and the planting of vegetative ground cover on slopes to prevent erosion. The reinforcing steel in the essential service water cooling tower foundation is to be cut off approximately eight inches above the concrete surface and the founda-tion covered with backfill to bring the area up to grade leve Based on review of the licensee's approved plans and drawings in this area, the inspector has determined that they meet the licensee's commitments stated in ULNRC-575 and that no further Region III inspection activity is require .

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.. . Exit Interview The inspector met with licensee representatives denoted in Paragraph 1

.at the conclusion of the inspection and discussed the likely content of

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the inspection repor The licensee representatives did not indicate that any of the information disclosed during the inspection could be proprietar