IR 05000263/1977012
| ML20024G498 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/21/1977 |
| From: | Choules N, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G494 | List: |
| References | |
| 50-263-77-12, IEB-77-01, IEB-77-1, NUDOCS 9102120569 | |
| Download: ML20024G498 (6) | |
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l!.S. NUCLE AR REGULA10RY C04til SS10!l I (
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OTFICC OF I!1SPECT10N AND r.Nf0RCE!1Cftf REC 10N III Report No. 5p-263/77-12 Docket No. 50-263 License No. DPR-22
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Licensee:
Northern States Power Company 414 Nicollet Mall Minneapolis, MN $5401 Facility Natne:
Monticello Nuclear Gene',ating plant Inspection At: Monticello Site, Monticello, MN Inspection conducted:
July 5-8, 1977
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Inspector:
N. C. Choules date signed
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Approved By:
R. F. k'a rnick, Chie f Reactor Projects Section date signed Inspection Summary Inspection on July 5-8, 1977 (report No. 50-263/77-12)
Areas inspected:
Roatine, unannounced inpocction of plant operations, cleanliness, nonroutine event reports, IE Bulletin fellovup, out-standing itens, and independent inspection.
The inspection included 27 inspector-hours onsite by one URC inspector.
Results:
No items of noncompliance or deviations were identified.
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9102120569 770722 PDR ADOCK 05000263 G
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DETAILS
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1.
Persons Contacted
- M. H. Clarity, Superintendent, Plant Engineering and Radiation Protection
- W. E. Anderson, Superintendent, Operations and Maintenance D. D. Antony, Plant Engineer, Operar. ions
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P. A. Pochop, Quality Assurance Engineer R. A Knitch, Shift Supervisor J. K. Pasch, Training Supervisor The inspector also talked with and interviewed several other licensee employees, including members of the Operations and Engineering sections.
- denotes those present at exit interview.
2.
Pl c.n t operations a.
Plant Tour (1) The inspector performed a plant tour accompanied by a licensee representative. The housekeepin; in the plant was adequate with the exception of the terus area uhcre a construction activity had tn a completed. The license's (
had this area cleaned up trior to the completien of the inspection.
(2) Selected " HOLD" and " SECURE" tcgs as lir,ted in the status log were reviewed to determine if they were properly approved and hung on equipment specified in the status log. All tags reviewed were found to be properly approved, hung, and accounted for in accordance with the
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licensee's Administrative Proccdures.
(3)
Selected valves for the core spray system were checked for proper alignment and no discrepencies vcre noted.
(4) The inspector revicued the status of annunciators which were lit in the control room with a control room operator.
Adequate explanations were given as to why these
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annunciators were lit.
b.
The jumper-bypass log was reviewed and no discrepancies were noted.
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Logbook s The inspector reviewed the control room reactor log and the shift supervisor log for selected days during the period March 15 to July 6, 1977, and confirmed that entries were illled out and initialed, that entrics gave suf ficient details to identify the action..and that management was initialing the' log sheets indicating their review.
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d.
Night Order Dock
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The subject orders were reviewed for the period March 15 to July 7, 1977, and no discrepancies were noted.
c.
Management Hemos The subject memos which were in ef fect were reviewed and no i
l discrepancies were noted.
f.
Volume F Temporary Memos The licensee had 15 subject memos in ef fect.
From the inspector's
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review of thece memos, it appeared that most of them could be incorporated into permanent operating procedures. In the exit interview, the licencee stated they would review this.
g.
Sirnlficant Operating Events (SOEs)
The following SOEs were reviewed and no items of concern were i
identified.
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Failure of No. 2 Starting System ( 1 )'
H-50E-77-04
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r of No. 11 Diesel Generator Scram Due to Loss of No. 12 Inter-(2) M-SOC-77-06
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ruptible MC Set i
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Resetor Coolant Chemistry Subject surveillance test (ST) records reviewed for the i
period March 15 to June 16, 1977 are as follows:
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Reactor Coolant Iodino-131 Dose (1) ST 0122
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Equivalent Activity Reactor Coolant Chloride / Conductivity (2) ST 0125
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Review of those records indicated:
(1) No evidence of (uel failure; and (2) Conductivity and chloride concentrations were maintained below the Technical Specifications limit.
3.
Reportable Occurrences
RO 77-121/ and the licensee's actions associated with thic occurrence were reviewed with the licensee.
No items of concern were identified.
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RO 77-062/ was reviewed in the office and is considered closed.
4.
Cleanliness The inspector visually inspected the housekeeping and cleanliness during the plant tour (Paragraph 2).
Two licensee perronnel responsible for cleanup of certain areas of the plant were interviewed to determine if they understood their cleaning and housekeeping terponsibilities.
No discrep-ancies were noted in the irterviews.
5.
IE Pulletin 77-01 (
The inspector verified that the pneumatic time delay relays used in the safety related systems have a repeat accuraeg range of 10% or beter as stated in the licensee's response f to the
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subject bulletin by review of specifications in vendor catalogs.
6.
Miscellaneous and Outstandine Itens R0_77-0Cb Air Ejecto-Moniters Fourd Inoperable a.
This occurrence was previously reviewed.5/ The inspector reviewed the licenree's follow-up actions regarding revision of the work request procedure and investigation of the sample 1/ RO 50-263/77-12, t:SP to Rill, dtd 6/27/77.
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2/ RO 50-263/77-08, NSP to RIII, dtd 6/29/77.
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3/ Ltr, NSP to Rill, dtd 5/27/77.
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4/ RO 50-263/77-06, NSP to R111, dtd 4/4/77.
5/ IE Inspection Rpt No. 50-263/77-05.
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flow alarm. The licensee has revised Administrative Control Directive ACD 3.6, Work Request Authorizations, to require tighter controls on work requests which are authorized to be started and then are delayed.
The licensee has investigated the flow alarm problem associated wth tilis occurrence and determined that improved flow detection instrumentation should be installed and is now in the process of obtaining such. This occurrence is considered closed.
b.
Control Rod Drive Hydraulic Return 1.ine Modification General Electric Company (CE) has made certain recom-n.endations to licensece regarding the CRD hydrauff e return line to prevent cracking due to thermal cycling.-
The licensec has performed a test recommended by CE to determine whether or not CRDs operate properly with the return flow valve off. The test showed the CRDu can be operated pro-perly with the return valve closed.
The licensco is currently operating with the return valve closed and is evaluating the possibility of rerouting the CRD line and copping the return nozzle.
c.
0A Audit Review The inspector reviewed several licensee QA audits conducted
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during the past nine months. One of the audits identified that the Preventative !!aintenance Program was not completely implemented. The licensee stated in the exit interview that they plan to complete ieptementation in the near future.
The inspector noted from review of audit reports and dis-cussions with the licensee representative that the licensee is increasing his on-the-job audits of work activities.
d.
Operations Connittee Minutes Review Subject minutes for the past four months were reviewed by the inspector. Attached to these ninutes were Radiation Occurrence Reports, which had been reviewed by the Committec.
While reviewing these reports, the inspector noted that the licensec had identified and corrected one item of noncompliance with respect to Technical Specifications.
6/ Cencral Elect ric Company Service Information 1.etters sib 200.
~ dtd 10/29/76, and SIL 200, SUP.1, dtd 3/25/77.
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c.
Work In progress During the tour of the plant, the inspector noted that the licensee was in the process of installing a new trolley on j
the reactor building crane. The Division of Operating Reactors approved modifications to'the reactor building crane in a letter to the licensee dated May 19. 1977.
The inspection also reviewed the installation of temporary air compressor with the licensee. This air comprescor was installed because the licensee's large installed air com-pressor was inoperable due to a hole in the piston. The air compressors provide instroment air and service ai'r to the plant.
No items of concern were identified by the inspector.
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7.
Exit Interview The inspecter met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspecton on July 8, 1977. The inspector sunmarized the scope and findings of the inspection.
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