ML20215J352
| ML20215J352 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/17/1987 |
| From: | Alexion T Office of Nuclear Reactor Regulation |
| To: | Crutchfield D, Rossi C, Shao L Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, IEB-85-003, IEB-85-3, NUDOCS 8706240407 | |
| Download: ML20215J352 (6) | |
Text
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55 17190I
,y MEMORANDUM FOR:
Dennis M. Crutchfield, Director DISTRIBUTION:
Division of Reactor Projects III, IV, V xDocket files;
& Special Projects NRC PDR c
Local PDR Lawrence C. Shao, Director GHolahan Division of Engineering TAlexion and Systems Technology PKreutzer PDIII-3 r/f Charles E. Rossi, Director Division of Operational Events Assessment Frank J. Congel, Director Division of Radiation Protection and Emergency Preparedness Jack W. Roe, Director Division of Licensee Performance and Quality Evaluation THRU:
David L. Wigginton, Acting Project Director Project Directorate III-3 Division of Reactor Projects FROM:
Thomas W. Alexion, Project Manager Project Directorate III-3 DivfS en of hector Projects i
Enclosed is a draft of NRR's SALP inm:t far Mianay covePing Union Electric Company (UE) licensing activities for the period from June 1, 1986 through May 31, 1987. The re rt is based on inputs provided by NRR reviewers and f
observations by NRR project management during their interactions with UE t
during the SALP period. A perforem atitis ut Category I has been assigned by the NRR SALP evalodion effort for the current licensing period.
Please review the draft assessment and provide any comments you feel are appropriate. Note that the new management directive regarding the goal of brevity was considered in preparing this draft. All connents received by June 26 will be considered for incorporation in the final report. Due to the short time available for connent, please provide your comments directly to the Callaway Project Manager, Tom Alexion, at X24730.
The NRC SALP Board meeting for Callaway is scheduled for July 22, 1987.
Thomas W. Alexion, Project Manager Project Directorate III-3 1
Division of Reactor Projects I
Enclosure:
I Draft NRR SALP Report cc: See next page 8706240407 870617 PDR ADOCK 0500 3
.I 3
cc:
T. Murley F. Miraglia R. Starostecki R. Lerch, RIII Office:
LA/PIIJ-3 PMf7 __,I"i i
3 SPE/PDIII-3 PD/PDIII-3 Surname: PKr r
TAl dn/tg MLynch DWi inton Date:
06/^ /87 06/ /87 06//9/87 06/ _ 87 i
i 0FFICE OF NUCLEAR REACTOR REGULATION INPUT FOR SALP 7 REPORT UNION ELECTRIC COMPANY CALLAWAY PLANT 1.
Licensing Activities (June 1, 1986 to May 31, 1987)
The basis for this appraisal was the licensee's performance in support of licensing actions (amendment requests, responses to generic letters and other actions) which have been reviewed and evaluated by the staff during the rating period. The subjects involved include the following:
Generic Reviews:
Plant Specific Reviews:
Generic Letter 83-28 Item 1.2)
Organizational Changes Generic letter 83-28 Item 2.1)
Surveillance Intervals-Analog Tests Generic Letter 83-28 Item 2.2)
MSIV and MFIV TS Changes Generic Letter 83-28 (Item 3.1.3/3.2.3) Containment Radiation Monitors 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 During the present rating period, the licensee's management 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 Connission'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 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.
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 significant additional information.
}
i
, I In the review of flow induced anomalous flux variations detected at 1
Callaway, the licensee provided prompt and technically sound responses to l
NRC concerns related to identifying the cause of the anomalous behavior.
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 assess the safety significance of this phenomenon.
A unique aspect of UE's approach to resolution of technical issues has been their interaction with Wolf Creek, the other SNUPPS standard plant.
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 information originally requested. The licensee was particularly responsive in providing additional information to assist the staff's review of the iodine filter exemption request.
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 failure mode, mechanism, and effect of failed components. Weaknesses of the LER's include the assessment of 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 (enforcements history, training and qualification effectiveness, and staffing), no basis exists for an NRR evaluation.
1 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 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 common link or trend being the percentage due to personnel errors or procedure inadequacies.
. Also in the functional area of plant operations, the following coment is offered as a result of a site visit on May 28, 1987. The staff toured several plant areas including the reactor building, turbine building, auxiliary building and the control room. The staff found that the plant was in good order with respect to cleanliness and housekeeping.
Activities in the control room were observed to be conducted in a highly professional manner with assigned personnel alert and attentive to duty.
Regarding other functional areas (maintenance, surveillance, etc.) no basis exists for an NRR evaluation.
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' RECORD OF MEETINGS AND OFFICIAL DOCUMENTS 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 Cycle 3 Reload and Uprating 04/29/87 2.
NRR Site Visits / Meetings Site visit to join Region III manages.ent 05/28/87 during their quarterly visit 3.
Commission Meetings None 4.
Schedular Exemptions Granted None 5.
Reliefs Granted None 6.
Exemptions Granted Exemption authorizing use of iodine filter 12/29/86 protection factors 7.
License Amendments Issued Organizational Changes (Amendment 16) 09/08/86 Surveillance Intervals for Analog Tests (Amendment 17) 09/08/86 MSIV and MFIV Tech Spec Charets (Amendment 18) 03/10/87 Generic Letter 83-28 Item 4.3 TS (Amendment 19) 04/03/87 Containment Radiation Monitors (Amendment 20) 04/10/87 DieselGeneratorTechSpecs(Amendment 21) 05/01/87 ESFResponseTimes_(Amendment 22) 05/04/87 Spent Fuel Pool (Amendment 23) 05/22/87 8.
Emergency Technical Specifications Changes ESFResponseTimes(Amendment 22) 9.
Orders Issued None
- 10. NRR/ Licensee Management Conferences None