ML20235H460
| ML20235H460 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 07/02/1987 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8707150145 | |
| Download: ML20235H460 (5) | |
Text
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Jul. 0 21987 Docket No. 50-483 "Ch[.
9 S fdh;i[dirgdoP[ts' MEMORANDUM FOR:
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" Division /of/Rea'ctor' Projec
'RegionLIII h, V 10 THRU:
David L. Wigginton, Acting Director Project Directorate III-3 Division of Reactor Projects FROM:
Thomas W. Alexion, Project Manager Project Directorate III-3 Division of Reactor Projects
SUBJECT:
NRR SALP REPORT - CALLAWAY Enclosed is NRR's input for the SALP Board meeting regarding Callaway, currently scheduled for July 22, 1987. Our evaluation was conducted according to NRR Office Letter No. 44 dated January 3, 1984 and NRC Manual Chapter 0516, Systematic Assessment of Licensee Performance, h/
Thomas W. Alexion, Project Manager Project Directorate III-3 Division of Reactor Projects
Enclosure:
As stated kQ DISTRIBUTION:
- Docket Filesy, NRC~PDR
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Local PDR PDIII-3 r/f OGC-Bethesda EJordan BGrimes JPartlow PKreutzer TAlexion
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Office:
Legf/III-3 PM PD PDIII-3 Surname: PK/efitzer TAl,e o /tg DWigginton Date:
OJP///87 f,1l/87 Q Q /87 8707150145 870702 DR ADOCK 0500 3
3 OFFICE OF NUCLEAR REACTOR REGULATION INPUT FOR SALP 7 REPORT.
UNION ELECTRIC COMPANY CALLAWAY PLANT 1.
Licensing Activities (June 1, 1986 to May 31, 1987) l The basis for this appraisal was the licensee's performance-in support of licensingactions(amendmentrequests,responsestogenericlettersand other actions) which have been reviewed and evaluated by.the staff during.
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the rating period. These actions have resulted in eight license amendments H
resulting in changes to the technical specifications. (one amendment was issued on an emergency basis) and one exemption to 10 CFR Part 20, Appendix A.
The subjects involved: include the following:
Generic Reviews:
Plant Specific Reviews:
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Generic Letter 83-28 (Item 1.2)
Organizational Changes 4
Generic Letter 83-28 (Item 2.1)
Surveillance Intervals-Analog. Tests GenericLetter83-28(Item 2.2)
MSIV and MFIV TS Changes Generic letter 83-28 (Item 3.1.3/3.2.3) Containment Radiation Monitors I
Generic Letter 83-28 (Item 4.3 TS)
Diesel Generator Tech. Specs.
Pressurized Thermal Shock ESF Response Times DCRDR Function and Task Analysis Spent Fuel Pool-Iodine Filter Exemption
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During the present rating period, the licensee's'managerent demonstrated active participation in licensing activities and kept abreast of all current and anticipated licensing actions.
In addition, the management's involvement in licensing activities assured timely response to the requirements of the Comission's requirements related to Generic Letter 83-28. The submittals have generally been of high quality and have not required significant rework to satisfy staff requirements. Management involvement related to the iodine filter exemption request was extensive and showed careful planning and preparation for the complex technical issues and administrative matters involved. Concern over quality assurance related to GRM-I cannister use is evident for both onsite and i
vendor programs.
The UE management has been an active participant in Owners Group activities intended to delete unnecessary issues from the technical specifications.
In particular Callaway has been volunteered to serve as a lead plant in the area of fire protection program improvements to the standard technical specifications.
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The UE management and its staff have demonstrated extensive technical expertise in all technical areas involving licensing actions.
In the review of Generic Letter 83-28, the staff noted that UE's approach was-direct and enabled ready verification of the acceptability of their program.
Their submittals indicated an understanding of the safety issues that were involved and permitted the staff to resolve the issue without requiring 4
significant additional information.
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2 In the review of flow induced anomalous flux variations detected at Callaway, the licensee provided prompt and technically sound responses to NRC. concerns related to identifying the cause of the anomalous behavior.
i UE made a presentation to NRC management and staff regarding the flux anomalies and kept NRC aware of the results of their investigations.
This cooperation with the staff was very helpful in. allowing the. staff to j
assess the safety significance of this phenomenon.
1 A unique aspect of UE's approach to resolution of technical issues has-been their interaction with Wolf Creek,_ the other SNUPPS standard plant.
l-Continued observation of problems and participation in the development of solutions for both plants.have permitted UE to pre-plan their approach to problems that are common to both plants.-
UE has been responsive to NRC requirements and requests. They have provided the information that the staff has requested in a timely manner. Their responses have generally been complete so that the staff has not been required to make additional requests to obtain the infomation originally requested. The licensee was particularly responsive in providing additional information to assist the staff's review of_ the iodine filter exemption reques t.
Regarding the Licensee Event Reports (LER's) submitted during the rating period, the overall quality of the submittals is:above average. Strengths of the Callaway LER's include the discussion concerning the method of 1
discovery, operator actions, failure mode, failure mechanism, and effect of failed components. Weaknesses of the LER's include the assessment of f
the safety consequences of the event and the corrective actions planned, especially those actions planned to prevent recurrence.
Regarding other criteria in the functional area of licensing activities (enforcement history, training and qualification effectiveness, and-staffing), no basis exists for an NRR evaluation.
2.
Conclusion A complete performance rating of Category 1 has been assigned by the NRR SALP evaluation effort for the current rating period in the functional area of licensing. activities.
3.
Other Functional Areas l
In NRR's review of LER's, the following comments are offered in the functional-area of plant operations. About 50% of the problems reported during the rating period involve either personnel errors or procedure inadequacies.
While the plant is still relatively new, this percentage appears to be higher than it should be. Also, with the exception of three of the LER's, involving failures to provide appropriate fire watches, the LERs appear to cover a broad range of subjects, with the only comon link or trend being the percentage due to personnel errors ur procedure inadequacies.
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, l Also in the functional area of plant operations, the following comment is offered as a result of a site visit on May 28, 1987. The staff toured i
several plant areas including the reactor building, turbine building, I
ausiliary building and the control room.
The staff found that the plant l
was in good order with respect to cleanliness and housekeeping.
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Activities in the control room were observed to be conducted in a highly professional manner with assigned personnel alert and attentive to duty.
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.Regarding other functional areas (maintenance, surveillance, etc.), no l
basis exists for an NRR evaluation.
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[ L RECORD OF MEETINGS AND OFFICIAL DOCUMENTS 1
1.
NRR/ Licensee Meetings Inservice Testing of Pumps and Valves 09/10/86 Flux and Flow Anomaly 01/16/87 Response to IE Bulletin 85-03 02/19/87
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Cycle 3 Reload and Uprating 04/29/87 2.
NRR Site Visits / Meetings Site visit to join' Region. III management 05/28/87
'during their quarterly visit 3.
Conunission Meetings None 4.
Schedular Exemptions Granted None g
5.
Reliefs Granted bene 6.
Exemptions Granted Exemption authorizing use of iodine filter 12/29/86 protection factors 7.
License Amendments Issued f
OrganizationalChanges(Amendment 16) 09/08/86 Surveillance Intervals for Analog Tests (Amendment 17)09/08/86 MSIV and MFIV Tech Spec Changes (Amendment 18) 03/10/87 Generic Letter 83-28 Item 4.3 TS (Amendment 19 04/03/87 ContainmentRadiationMonitors(Amendment 20))
04/10/87 DieselGeneratorTechSpecs(Amendment 21) 05/01/87 ESF Response Times (Amendment 22) 05/04/87 Spent Fuel Pool (Amendment 23) 05/22/87 8.
Emergency Technical Specifications Changes ESF Response Times.(Amendment 22)
'9.
Orders Issued None
- 10. NRR/ Licensee Management Conferences None l
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