ML18068A457
| ML18068A457 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 10/14/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18068A456 | List: |
| References | |
| NUDOCS 9810200176 | |
| Download: ML18068A457 (5) | |
Text
- ,
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE THIRD TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN
1.0 INTRODUCTION
AND.ASSOCIATED REQUESTS FOR RELIEF1 CONSUMERS ENERGY COMPANY2 PALISADES PLANT DOCKET NO. 50-255 The Technical Specifications (TS) for the Palisades Plant state that the inservice inspection of the 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 (B&PV) 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). 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements 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 pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for lnservice 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 examination of *components ~nd system pressure tests conducted during the first ten-year interval and subsequent intervals 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) twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of 1This corrected safety evaluation supersedes the staff's January 9, 1997, safety evaluation related to the Palisades Plant third ten year interval inservice inspection program plan and associated requests for relief. Revised text is indicated by change bars on the right margin.
2The company name was changed from Consumers Power Company on July 21, 1997, by Amendment No. 176 to Facility Operating License No. DPR-20.
9810200176 981014 PDR ADOCK 05000255 P
PDR ENCLOSURE I
the ASME Code for the Palisades third ten-year inservice inspection (ISi) interval is the 198.9 edition. The Palisades third ten-year interval commenced on May 12, 1995.
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 its 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 1 O CFR 50.55a(g)(6)(i), the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
In a letter dated September 6, 1995, Consumers Power Company (the licensee), submitted to the NRC its third ten-year inservice inspection interval program plan and associated requests for relief for Palisades. The licensee provided additional information by letters dated February 19 and June 24, 1996.
2.0 EVALUATION AND CONCLUSIONS The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the information provided by the licensee in support of its third ten-year inservice inspection interval program plan and associated requests for relief for Palisades. Based on the information submitted, the staff adopts the contractor's conclusions and recommendations presented in the attached Technical Evaluation Report (TER).
The staff has concluded no deviations from regulatory requirements or commitments were identified in the licensee's Third Ten-Year Interval Program Plan, Revision 0 for Palisades. For Requests for Relief Nos. RR-01, RR-02, RR-03, RR-05, RR-06 (Parts 1 and 2), RR-07, and RR-08 the staff concluded that: (1) the Code requirements contained in the above requests for relief are impractical; (2) the subject components would be required to be redesigned; (3) if the Code requirements were imposed it wou_ld result in a burden on the licensee; and (4) the proposed inspections contained in the subject requests for relief provide reasonable assurance of operational readiness of the subject systems. Therefore, pursuant to 10 CFR 50.55a(g)(6)(i)
Requests for Relief Nos. RR-01, RR-02, RR-03, RR-05, RR-06 (Parts 1 and 2), RR-07, and RR-08 are granted as requested.
The licensee's proposed alternative to use Code Case N-524 contained in Request for Relief No. RR-10 provides an acceptable level of.quality and safety. Therefore, the licensee's proposed alternative to use Code Case N-524 is authorized pursuant 10 CFR 50.55a(a)(3)(i),
provided that all requirements of Code Case N-524 are satisfied. Code Case N-524 is authorized for the current interval or until such time as the Code case is published in a future revision of Regulatory Guide (RG) 1.147, "lnservice Inspection Code Case Acceptability -
ASME Section XI, Div. 1." At that time, if the licensee intends to continue to implement this Code case*, the licensee is to follow all provisions in Code Case N-524 with limitations issued in RG 1.147, if any.
Compliance with the Code res:1uirement contained in Request for Relief No. RR-11 would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The licensee's proposed alternative to perform manual examinations from the inside surface of the reactor pressure vessel (RPV) lower head meridional welds provides reasonable assurance of operational readiness of the RPV lower head meridional welds. Therefore, the licensee's proposed alternative is authorized pursuant to 1 O CFR 50.55a(a)(3)(ii) as requested.
Request for Relief No. RR-04 is denied because the basis for relief from the Code requirements was based on estimated coverages not on actual coverages. The licensee may consider resubmitting its request for relief when the actual coverage is obtained. Request for Relief No.
RR-09 was withdrawn by the licensee in its letter dated June 24, 1996.3
Attachment:
INEL Technical Evaluation Report Principal Contributor: T. Mclellan Date: January 9, 1997 Corrected: October 14, 1998 3By letter dated June 3, 1997, the licensee resubmitted Requests for Relief RR-4 and RR-9. The staff evaluation of the resubmitted relief requests was provided in a safety evaluation dated March 20, 1998.
PALISADES NUCLEAR PLANT Page 1 of 2 Third 10-Year ISi Interval TABLE 1 su""ARY OF RELIEF REQUESTS Relief lel fef Request Sy&tm or Ex*
ltm Voltme or Aree to be R~ired LfcenHe Proposed
- ~t llullJer Cmponent category No.
Ex*ined Method Alternative Status RR-1 Class 1 Piping 8-J
\\lelds:
VollJlletric Perform a volunetric Granted "elds 89.11 PCS-42-RCL-1H-1, 2 and Surface examination of the outside PCS-42-RCL-2H-1, 2.
surface from the Inside of PCS-30-RCL-1A-15, -16 the pipe with a mechanized PCS-30-RCL-18-13, -14 system PCS-30-RCL-2A-14, -15 PCS-30-RCL-28-14, -15 89.12 PCS-30-RCL-1A-15LD-1, 15LD-2 PCS-30-RCL-1A-16LU-1, 16LU-2 PCS-30-RCL-18-13LD-1, 13LD-2 PCS-30-RCL-18-14LU-1, 14LU-2 PCS-30-RCL-2A-14LD-1, 14LD-2 PCS-3D-RCL-2A-15LU-1, 15LU-2 PCS-30-RCL-28-14LU-1, 14LU-2 PCS-30-RCL-28-14LD-1, 14LD-2 PCS-30-RCL-28*15LU-1, 15LU-2 RR-2 Reactor 8-A 81.40 Head-to-Flange "eld VollJlletric Examine to the extent Granted Pressure Vessel and Surface practical RR-3 Steam Generator C-A C1.10 Shell "elds: 1. 101-221 and VollJlletric Examine to the extent Granted 2-101-221 practical RR-4 Steam Generator 8-D 83.130 Nozzle-to-Shell "elds: 1.20-VollJlletric Examine to the extent Denied-251, 1-102-251A, 1-102-2518, practical Coverages 2-104-351, 2-102-351A, 2-were 102-3518 estimated only
PALISADES NUCLEAR PLANT Page 2 of 2 Third 10-Year ISi Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief lelief R~t Syste11 or Ex*
ltt!ll Yol..-e or Are11 to be l~ired licensee Proposed
- ~t Mtaber Colpnent Category llo.
Ex*ined Method Al terneti'we Status RR*5 Regenerative 8*0
- 83. 150 Nozzle*to*Shell Melds:
Volunetric Examine to the extent Granted Heat Exchanger E*56*A and E*56*8, Melds 05 practical and 07 83.160 Nozzle Inner Radius Sections: E*56*A and E*56*
8, Melds 05 RR*6 Pressurizer 8*8 82.21 Shell and Head Melds: 5-988, Vollllletrfc Examine to the extent Granted 82.22 3*982, 2*984, 1*9S3A*D, 1*
practical 8*D 984A*D 83.110 Nozzle Melds: 1*986, 3*985, 8*986, 8*986A*C RR*7 Shutdown C*A C1.10 Shell-to-Flange Meld:
Voli.netric Examine to the extent Granted Cooling Heat HX E-60*8/Meld 01 practical Exchanger C1.30 Tubesheet*to*shell Meld:
HX E-60*8/Meld 02 C*8 C2.21 Nozzle-to-Shell Melds:
HX E-60*8/Meld 03 HX E-60*8/Meld 04 RR-8 Reactor 8*A 81.21 Closure Head Meld 6*1188 Voli.netric Perform VT-2 during system Granted Pressure Vessel leakage test RR-9 Reactor 8*D 83.90 NA NA NA Withdrawn Pressure Vessel
- 83. 100 RR-10 Class 1 and 2 8-J 89.12 Longitudinal Pipe Melds Volunetric l111>lement alternatives Authorized Piping C*F*1 C5.12 and/or contained in Code Case N-524 C*F*2 C5.22 Surf ace as C5.52 Applicable C5.62 RR-11 Reactor 8*A 81.22 Lower Head Meridional Melds:
Volunetric Examine to the extent Authorized Pressure Vessel 1*113A through 1*113F practical