ML18057B260
| ML18057B260 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 09/03/1991 |
| From: | Brian Holian Office of Nuclear Reactor Regulation |
| To: | Slade G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML18057B261 | List: |
| References | |
| TAC-72622, NUDOCS 9109120208 | |
| Download: ML18057B260 (7) | |
Text
Docket No. 50-255 Mr. Gerald B. Slade Plant General Manager Palisades Plant Consumers Power Company UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 September 3, 1991 27780 Blue Star Memorial Highway Covert, Michigan 49043
Dear Mr. Slade:
SUBJECT:
SAFETY EVALUATION OF THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF FOR PALISADES NUCLEAR PLANT, (TAC NO. 72622)
The initial Inservice Inspection (!SI) program for the Second Ten-Year Interval Inservice Inspection Program Plan, Revision 1, with associated requests for relief, was submitted to the NRC by the Consumers Power Company by letter dated December 19, 1988. The NRC requested additional information to complete the review of the !SI program and relief requests. This information was furnished as attachments to letters dated March 29 and July 13, 1990. The program plan was submitted for review and evaluation of its compliance with the requirements of the 1983 Edition including Addenda through Sunaner 1983 of Section XI of the ASME Boiler & Pressure Vessel Code, Regulations, and plant Technical Specifications.
The NRC Staff, with technical assistance from the Idaho National Engineering Laboratory (INEL), has reviewed and evaluated the program plan, additional information provided, and requests for relief from some Section XI requirements that the licensee determined to be impractical to perform at the facility.
Based on the information submitted, the staff agrees with the contractor's conclusions and reconunendations presented in the Technical Evaluation Report (TER) enclosed.
We have determined that the Second Ten-Year Interval Inservice Inspection Program, Revision 1 for the Palisades Nuclear Plant is in compliance with 10 CFR 50.55a.
We have also determined that Section XI Code requirements for examination of some components cited by the licensee are impractical to perform at the Palisades Nuclear Plant and we have granted relief from those
( 9109120208 910903 PDR ADOCK 05000255 PDR COPY
Mr. G. September 3, 1991 requirements.
In cases where the necessary findings could not be made, we have denied the requests or determined that relief was not required. A summary of the requirements and the bases for our conclusions are contained in the enclosed safety evaluation (SE).
Enclosures:
As Stated cc w/enclosure:
See next page DISTRIBUTION:
Dpcket Fi le NRG & Local PDRs PD3-1 rdg. file B. Boger J. Zwolinski P. Shuttleworth B. Holian D. E. Smith OGG Sincerely, Original signed by Brian Holian, Project Manager Project Directorate 111-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation E. Jordan MNBB-3701 D. Smith 7 04 ACRS (10)
Palisades Plant File B. Clayton Riii LA: PD I 11-1 P.iShutt 1 ew~~}Y A t:!t {.fJ/91 ${!V"'L,,
Official Record Copy:
PM:PD III-1 ~ D:PD III-1 {}vl B. Holian 'Oltl L. Marsh
'b!4!J/91 1)/3 /91 Tac 72622/Palisades
Mr. Gerald B. Slade Consumers Power Company cc:
M. I. Miller, Esquire Sidley & Austin 54th Floor One First National Plaza Chicago, Illinois 60603 Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Jerry Sarno Township Supervisor Covert Township 36197 M-140 Highway Covert, Michigan 49043 Office of the Governor Room 1 - Capitol Building Lansing, Michigan 48913 Mr. Patrick M. Donnelly Director, Safety and Licensing Palisades Plant 27780 Blue Star Memorial Hwy.
Covert, Michigan 49043 Resident Inspector c/o U.S. Nuclear Regulatory Conunission Palisades Plant 27782 Blue Star Memorial Hwy.
Covert, Michigan 49043 Palisades Plant Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health P.O. Box 30035 Lansing, Michigan 48909 Gerald Charnoff, P.C.
Shaw, Pittman, Potts &
Trowbridge 2300 N. Street, N.W.
Washington, D.C.
20037 Mr. David L. Brannen Vice President Palisades Generating Company c/o Bechtel Power Corporation 15740 Shady Grove Road Gaithersburg, Maryland 20877 Roy W. Jone*s Manager, Strategic Program Development Westinghouse Electric Corporation 4350 Northern Pike Monroeville, Pennsylvania 15146
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN CONSUMERS POWER COMPANY PALISADES NUCLEAR PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
Technical Specification 4.0.5 for the Palisades Nuclear Plant states that inservice inspection of American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Subsection 50.55a(a)(3) of 10 CFR states that alternatives to the requirements of paragraph (g) may be used if (i) the proposed alternatives would provide an acceptable level of quality or safety, or (ii) compliance with the specified requirements of this section would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a{g){4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The regulations require that inservice examinations of components and system pressure tests conducted during the second ten-year interval comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to the start of the 120-month inspection interval, subject to the limitations and modification) listed therein. The components (including supports) may meet the requir~~ants set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for his facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a{g)(6)(i) or, alternatively, 10 CFR 50.55a(a)(3), the Commission may grant relief and may impose alternative requirements as it determines 9109i2021T 91090:3 ____ -- - ---~-
PDR ADOCK 05000255 PDR is authorized by law, will not endanger life, property, or the corrmon defense and security, and is otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facilty.
The licensee, Consumers Power Company, has prepared the Palisades Nuclear Plant Second Ten-Year Interval Inservice Inspection (ISi) Program and Plan to meet the requirements of the 1983 Edition, Surrmer 1983 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code, except that the extent of examination of Class 2 piping welds has been determined by the 1974 Edition and Addenda through the Sunnner 1975 Addenda as required by 10 CFR 50.55a(b)(2)(iv)(B). The staff, with technical assistance from its Contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the Second Ten-Year Interval Inservice Inspection Program, additional information related to the Program and Plan, and the requests for relief from certain ASME Code requirements determined to be impractical for Palisades Nuclear Plant during the second inspection interval.
2.0 EVALUATION The ISi Program and Plan have been evaluated for (a) application of the correct Section XI Code edition and addenda, (b) compliance with examination and test requirements of Section XI, (c) acceptability of the examination sample, (d) compliance with prior ISI corrmitments made by the licensee, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from certain Section XI Code requirements deemed impractical by the licensee. The staff has determined that the licensee's ISi Program Plan reflects compliance with the requirements listed above.
The information provided by the licensee in support of requests for relief from certain Section XI requirements has been evaluated and the bases for granting relief from those requirements are documented in the attached INEL Technical Evaluation Report EGG-MS-9172.
We concur with the findings and recommendations contained in the subject report.
We have determined that relief is not required for Relief Request RR-1.
Pursuant to 10 CFR 50.55a(g)(6)(i), relief is granted with conditions stated in the TER for Relief Requests RR-2 and RR-3.
Pursuant to 10 CFR 50.55a(a)(3)(ii), relief is granted with conditions stated in the TER for Relief Reques~ :rn-4. Table 1 presents a summary of the reliefs requested and the status of the requests as determined by the staff.
- 3. 0 CONCLUSION The staff concludes that the Palisades Nuclear Plant Second Ten-Year Interval Inservice Inspection Program and Plan, with the additional information provided and the specific written relief, constitutes the basis for compliance with 10 CFR 50.55a(g) and Technical Specification 4.0.5 and is, therefore, acceptable.
Palisades Nuclear Plant Page 1 of 2 TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Licensee Request System or Exam.
Item Volume or Area Required Proposed Relief Request Number Component Cat.
No.
to be Examined Method Alternative Status RR-1 RPV B-G-2 B7.80 Control rod drive (CRD)
VT-1 Visual None.
VT-1 Relief not Control bolting other than the visual exam when Required Rod Drive peripheral CRD housing disassembled for bolting maintenance RR-2 Class 1 B-J 89.11 Class 1 pressure Volumetric Automated 100%
Granted with Piping*
B9.12 retaining piping welds:
and surf ace volumetric exam con.ditions PCS-42-RCL-lH-1 exam from piping ID stated in PCS-42-RCL-2H-1 Technical PCS-30-RCL-lA, 16LU-1, Evaluation 16LU-2, Report
& 16 PCS-30-RCL-lB, 14LU-1, 14LU-2,
& 14 PCS-30-RCL-2A, 15LU-1, 15LU-2,
& 15 PCS-30-RCL-2B, 15LU-1, 15LU-2,
& 15 RR-3 Reactor B-L-1 B12.10 RC pump casing welds Volumetric None Granted with Coolant Exam conditions Pumps stated in Technical Evaluation Report
Palisades Nuclear Plant Page 2 of 2 Relief Request Number RR-4 System or Component Reactor Coolant Pumps Exam.
Cat.
B-L-2 Item No.
812.20 TABLE 1
SUMMARY
OF RELIEF REQUESTS Volume or Area to be Examined RC pump casing internal surf aces Required Method VT-3 visual exam Licensee Proposed Alternative None.
VT-3 visual exam to maximum extent practical if pump disassembled for maintenance Relief Request Status Granted with condition stated in Technical Evaluation Report