ML20196H934
| ML20196H934 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 03/04/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196H911 | List: |
| References | |
| NUDOCS 8803140111 | |
| Download: ML20196H934 (4) | |
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,$AFETY EVALUATION BY THE OFFICE OF huCLEAR REACTOR REGULATION RELATED TO THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PHILADELPHIA ELECTRIC COMPANY LIMERICK GENERATING STATION, UNIT 1 00CKET NO.: 50-352 l
INTRODUCTION The Technical Specifications for the Limerick Generating Station Unit 1 state that surveillance requirements for inservice inspection and testing of Arerican Society of Mechanical Engineers (ASME) Boiler and Pressure Yessel Code Class 1, 2 and 3 components shall be applicable as follows:
Inservice inspection of ASME Code Class 1, 2 and 3 components shall be perfonned in accordance with Section XI of the ASME Code and applicable Addenda as required by 10 CFR 50 Section 50.55a(g), except where specific wrf tten relief has been granted by the Comission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
Pursuant to 10 CFR 50a(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 exhmination 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.
In addition, inservice examination of components and systems pressure tests conducted during the First Ten-year interval shall comply with the requirements in the latest edition and addenda l
of Section XI of thE ASMf Code incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to the date of issuance of the operating license.
subject to the limitations and modifications listed therein. The components (including supports) may meet the requirements 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 confomance to an examination requirement of Sect. ion XI of the ASME Code is not practical for his facility, infomation is submitted to the Comission 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)(1), the Comission may grant relief and impose alternative requirements as it detemines are authorized by law and will not endanger life or property or the comon defense and security and are othenvise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed, The Philadelphia Electric Company (the licensee) prepared the Limerick a
Generating Station, Unit 1 and Common Plant, First Ten-year Interval Inservice l
Inspection Program, Revision 3, to meet the requirements of the ASME Code, 1
Section XI, 1980 Edition, including Winter 1981 Addenda except that the extent of examination for Class 2 piping welds is determined by(the 1974 Edition, including Sumer 1975 Addenda, pursuant to 10 CFR 50.55a b).
The First Ten-year began on February 1,1986, and ends February 1,1996.
9803140111 080304 PDR ADOCK 050 P
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2-Revision 1 of the First Ten-year Interval Inservice Inspection Program was submitted for staff review in October,1985.
Additional infortration was submitted by the Licensee, including requests for relief from impractical ASME Code requirements, on August 14, 1986 January 30, 1987, and August 11, 1987. The program was evaluated by the staff and their contractor, Idaho National Engineering Laboratory, for a) compliance with the appropriate ASME Code Section XI Edition and Addenda, b) acceptability of the examination sample, c) exclusion criteria, and d) compliance with augmented and/or other examination commitments identified during the licensing process.
EVALUATION The deteminations addressed by the Licensee in the First Ten-year Interval Inservice Inspection Program, Revision 3, and to staff's request for additional infomation that certain ASME Code requirement; were impractical to perfom at the Limerick Generating Station Unit 1 and Comon Plant were evaluated. A summary of our evaluation is shown in Table 1.
The detailed evaluation is attached in the report # rom our contractor, Idaho National Engineering Laboratory.
CONCLUSION We conclude from our evaluation that the First Ten-year Interval Inservice Inspection Program, Revision 3, for the Limerick Generating Station, Unit 1 and Comon Plant is acceptable and in compliance with 10 CFR 50.55a(g)(4).
We detemined that certain ASME Code Section XI examination requirements are impractical to perfom at the Limerick Generating Station, Unit I and Comon Plant. The Licensee has demonstrated that either the prepcsed alternative would provide an acceptable level of quality and safety or that compliance with the requirement would result in hardship and/or unusual difficulty withcut a compensating increase in the level of quality and safety.
Relief is granted from ASME Code Section XI requirements for request numbers 2.4.4,
- 2. 7.1, 2. 7. 2, 2. 7. 3, 3.1.1(1), 2.13.1, 3. 4.1, 3.4. 2, 3.4. 3, 3. 7.1, 3.1.1( 2 ),
3.10.1, 3.10.2 and 6.4.1.
The staff is in the process of reviewing the examination requirements for the reactor pressure vessel and relief is not granted for request numbers 2.4.1, 2.4.2. and 2.4.3, category B-A welds.
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Table 1 Status of Requests for Relief from ASME Code Requirefrents Request Examination Number Category Description Status 2.4.1 B-A Reactor Pressure Vessel Not granted Item B.1.11 Shell Circumferential Welds 2.4.2 B-A Reactor Pressure Yessel Not granted Item B.1.12 Shell Longitudinal Welds J
2.4.3 B-A Reactor Pressure Vessel Not granted Item Bl.30 Shell-to-Flange Weld 2.4.4 B-D Reactor Pressure Vessel Granted Item B3.90 Nozzle-to-Vessel Welds 2.7.1 B-F Class 1 Dissimilar Granted Item B5.130 Metal Circumferential Welds 2.7.2 B-J Class 1 Pressure Retaining Granted Item B9.11 Circumferential Welds in Piping 2.7.3 B-K-1 Integrally Welded Granted Item B10.10 Attachments in Class 1 Piping 3.1.1(1)
B-J Pressure Retaining Granted Items 89.11 Class 1 Welds in Piping and 89.21 within the "No Break" Boundaries 2.13.1 B-M-2 Class 1 Valve Granted Item B12.50 Bodies i
3.4.1 C-A RPR Peat Exchanger Granted Item C1.10 Shell Circumferential Weld 3.4.2 C-B RHR Heat Exchanger Granted Item C2.21 Nozzle Weld 3.4.3 C-C RHR Heat Exchanger Granted Item C3.10 Integrally Welded Attachments l
3.7.1 C-C Integrally Weided Granted Item C3.20 Attachinents on Class 2' piping 4
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i Table 1 Status of Requests for Relief from ASME Code Requirements Request Examination Nurber Category Description Status 3.1.1(2)
C-F Pressure Petaining Granted l
Item C5.21 Class 2 Piping Welds with "No Break" Boundaries 3.10.1 C-G RHR and Core Spray Granted Items C6.10 Pump Casing Welds 3.10.2 C-C RCIC Pump Casing Grarited Item C3.30 Integral Attachment Welds l
l 6.4.1 F-C Class 1, 2 and 3 Granted i
Items F3.10 Mechanical Snubbers through F3.50 i
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