ML20236A540
| ML20236A540 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/15/1987 |
| From: | Wagner D Office of Nuclear Reactor Regulation |
| To: | Crutchfield D, Rossi C, Shao L Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8710220346 | |
| Download: ML20236A540 (5) | |
Text
I
'o UNITED STATES
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October 15, 1987 l
l MEMORANDUM FOR:
Dennis M. Crutchfield, Director Division of Reactor Projects III, IV, V and Special Projects Lawrence C. Shao, Director Division of Engineering and Systems Technology l
l Charles E. Rossi, Director l
l 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 uality Evaluation THRU:
David igginton, Acting Director Proaect Directorate III-3 Division of Reactor Projects FROM:
David H. Wagner, Project Manager Project Directorate III-3 Division of Reactor Projects Enclosed is a draft of NRR's SALP input for Point Beach 1 & 2 covering Wisconsin Electric Power Company (WEPC0) licensing activities for the period from April 1,1986 through September 30, 1987. The report is based on inputs provided by NRR reviewers and observations by NRR project manage-ment during their interactions with WEPC0 during the SALP period. A perform-l ance rating of Category 2 has been assigned by the NRR SALP evaluation effort for the current period.
Please review the draft assessment and provide any comments you feel are appropriate. All comments received by October 23, 1987 will be considered for incorporation in the final reports. Due to the short time available for comment, please provide your connents directly to the Point Beach Project Manager, David Wagner, at x28158.
l B710220346 871015 PDR ADOCK 05000266 PDR
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.-The NRC SALP Board meeting for Point' Beach is scheduled for, November 23, 1987.
/s/
David H.' Wagner,' Project Manager Project Directorate III-3
. Division of Reactor _ Projects
Enclosure:
. Draft NRR SALP Report cc:.T. Colburn Distribution:
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Grey Files NRC & Local PDRs*
PDIII-3 r/f GHolahan DWagner PKreutzer KEPerkins t
Office:
LA/PDI,II-3 P!vf L
-3 PD/PDIII-3 Surname: PKfhltzer DWagner DWigginton Date:-
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1 0FFICE OF NUCLEAR REACTOR REGULATION INPUT FOR SALP 6 I
WISCONSIN ELECTRIC POWER COMPANY POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2
-1.
Licensing Activities (April 1, 1986 through September 30,1987)
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. These actions have resulted in 18 license amendments, I
a relief request, an exemption to 10 CFR Part 50 Appendix R, and other licensing actions.
The issues involved included the following:
Plant Specific:
Component Cooling Water Heat Exchanjiy T.S. change RPV Pressure / Temperature Limits T.S. R ange Draft SER, Procedures Generation Package Leaking Fuel Rod T.S. change RPV Flaw Component Cooling Water T.S. change Inservice Inspection Relief Replacement of Snubbers with Energy Absorbers Operating License Expiration Date Extension 1
Appendix R Exemption Generic Items Regulatory Guide 1.97, Post Accident Instrumentation Generic letter 85-19, Iodine Spiking TMI Action Item II.K.3.31, Compliance with 10 CFR 50.46 Generic letter 83-28, Item 4.5.2, Reactor Trip System Functional Testing Generic letter 83-28. Item 2.1 (Part 2), Vendor Interface Programs-RTS TMI Action Plan Item II.F.2. Inadequate Core Cooling Instrumentation During this rating period, the licensee's management appeared to be actively involved in licensing activities and appeared to remain abreast of current and anticipated licensing actions. Management involvement in licensing actions has resulted in timely responses to staff initiatives requiring responses by specified dates. These submittals, such as responses to
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Generic Letters and responses to staff questions regarding generic issues, are of good quality and sufficiently complete. Although the majority of applications for specific actions (TS amendments, plant-specific licensee
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issues) are of good quality, timely, and do not require significant rework to address staff requirements, a number of notable exceptions exist.
For example, late in this reporting cycle, the licensee sought NRR approval for the land-spread disposal of slightly radioactive sludge. Although this was considered a high-priority issue by the licensee, the staff was required to issue an extensive request for additional information to the licensee, in order to continue the review. The licensee's original application was in-I complete, despite the staff's referring the licensee to another utility's similar request for land-spread disposal of radioactive sludge as an example of a complete application. Additionally, in a letter dated September 10, 1987, the licensee sought NRC authorization for replacing a number of snubbers with energy absorbers during the Unit 2 outage, commencing October 2, 1987. The impact of this untimeliness is not known at this time. Although, the majority of submittals to the NRC are complete and timely, the licensee and its management should exert more effort to assure all licensing action applications are complete and timely.
j The technical content of license actions applications and responses to j
requests for additional information is generally quite good. However, as i
noted above, some of these actions have been submitted incomplete.
In most cases, requests for additional information resuit from incompleteness l
rcther than the technical content of the information provided. A number of l
i telephone conferences have taken place with the licensee during this rating period. The licensee has assured that the appropriate corporate / station personnel are on hand to discuss the issues. During the Unit I refueling outage in the spring of 1987, a flaw was discovered in the reactor pressure vessel. On a day's notice, the licensee flew to NRC-Bethesda to have a meeting (on Saturday) with the staff, in anticipation of restart the next day. The licensee brought along sufficient personnel to assure the issue was adequately addressed.
The Licensee Event Reports (LER's) submitted during the rating period are of good quality. Overall quality of the LER's has increased since the last SALP. Notable quality improvements were noted in the safety assess-ment section of the LER's. A particular strength of the LER's is that the licensee identifies similar events which may have been reported in previous LER's. However, a number of LER's lacked certain information considered necessary to complete a root cause discussion.
For example, stating that a specific component failed and was replaced is not adequate to satisfy the requirements concerning cause and corrective actions. The reason for 1
component failure must be stated, thereby allowing assessment of the corrective actions.
Regarding other criteria in the functional area of licensing activities (enforcement history, training and qualification effectiveness, and staffers), no basis exists for an NRR evaluation.
2.
Conclusion A complete performance rating of Category 2 has been assigned by the NRR SALP evaluation effort for the current rating period in the functional area of licensing activities.
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1 RECORDS MEETINGS AND OFFICIAL DOCllMENTS l
1 1.
NRR/ Licensee Meetings l
Energy Absorbers 10/23/86 Inservice Testing Program 03/16/87 RPV Flaw 05/30/87 l
2.
Coninission Meetings None I
3.
Schedular Exceptions Granted None 4.
Reliefs Granted ASME Section XI relief request regarding' 05/7/87 the shell-to-shell tubesheet and nozzle-to-shell welds in the non-regenerative heat exchangers.
5.
Exemptions Granted:
Exemption to Appendix R of 10 CFR 50, Section 12/31/87 III.G for various plant locations.
6.
License Amendments Issued.
Reactor Trip Breaker Surveillance 06/17/86 Component Cooling Water System (Amendments 101 06/25/86 and104)
Iodine Spiking (Amendments 102 and 105) 06/27/86 Reactor Coolant Pumps (Amendments 103 and 106) 07/03/86 Containment Integrated Leak Rate Testing 08/27/86 (Amendments 104 and 107)
Component Cooling Water System (Amendments 105 02/02/87 and 108)
Valve Surveillance Requirements (Amendments 106 03/03/87 and 109 03/17/87 Operating) License Extension (Amendments 107 and 110 Leaking Fuel Rod (Amendments 108 and 111) 05/27/87 7.
Emergency Technical Specification Changes None 8.
Orders Issued None
- 9. NRR/ Licensee Management Conferences None I
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