ML19283A214
| ML19283A214 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 08/18/1980 |
| From: | Pawlicki S Office of Nuclear Reactor Regulation |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8008260018 | |
| Download: ML19283A214 (6) | |
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AUG 16 IBM MEMORANDUM FOR:
B. J. Youngblood, Chief
,' Licensing Branch 1
! Division of Licensing FR0!!:
S. S. Pawlicki, Chief Materials Engineering Branch Division of Engineering
SUBJECT:
COMMONWEALTH EDISION COMPANY, LA SALLE COUNTY STATION UNITS 1 & 2 SAFETY EVALUATION REPORT ON PRESERVICE INSPECTION PROGRAM Plant Name: La Salle County Station, Unit Nos.1 & 2 Supplier: General Electric Company; Sargent & Lundy Docket Numbers:
50-373/374 Licensing Stage: OL Pesponsible Branch and Project Manager: LB 1; A. Bournia Reviewers:
M. Hum, J. Kennedy (T. Taylor, PNL)
Description of Task:
SER Input on Preservice Inspection Program Review Status:
Complete The Inservice Inspection Section of the Materials Engineering Branch, Division of Engineering is reviewing the preservice inspection program of La Salle Units 1 and 2 submitted by the Commonwealth Edision Company on March 15, 1979. Our input to the Safety Evaluation Report (Attachment 1) discusses the current status of this review. Requests for additional information and staff positions will be forthcoming at a later date.
fsA S. S. Pawlicki, Chief Materials Engineering Branch Division of Engineering
Contact:
J. Kennedy X29545 M. Hum X29491 cc:
See next Page 8 008060016
B. J. Youngblood AUG 181980 cc:
R. H. Vollmer D. G. Eisenhut R. A. Purple V. S. Noonan R. L. Tedesco S. S. Pawlicki B. D. Llaw R. M. Gamble W. S. Hazel ton A. Bournia MTEB Members M. Hum J. Kennedy
ATTACHMENT 1 COMMONWEALTH EDITION COMPAtlY LA SALLE COUNTY STATION UNIT N05. 1 & 2 DOCKET NUMBERS 50-373/374 SAFETY EVALUATION REPORT MATERIALS ENGINEERING BRANCH INSERVICE INSPECTION SECTION S.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing General Design Criterion 32, " Inspection of Reactor Coolant Pressure Boundary," Appendix A of CFR Part 50 requires, in part, that compo-nents which are part of the reactor coolant pressure boundary be de-signed to permit periodic inspection and testing of important areas and features to assess their structural and leaktight integrity.
To ensure that no deleterious defects develop during service, selected welds and weld heat-affected zones will be inspected periodically at La Salle Units 1 and 2.
The design of the ASME Code Class 1 components cf the reactor coolant pressure boundary in La Salle Units 1 and 2 incorporates provisions for access for inservice inspection in accor-dance with Section XI of the ASME Code. Methods have been developed to facilitate the remote inspection of those areas of the reactor vessel not readily accessible to inspection personnel.
Section 50.55a(g),10 CFR Part 50, defines the detailed requirements for the preservice and inservice-inspection programs for light water cooled nuclear power facility components.
Based upon a construction permit date of September 10, 1973, this section of the Code of Federal Regulations requires that a preservice inspection program be developed and implemented using at least the Edition and Addenda of Section XI of the ASME Code in effect six months prior to the date of issuance of the construction pennit. Also, the initial inservice inspection
. program must comply with the requirements of the latest Edition and Addenda of Section XI of the ASME Code in effect 12 months prior to the date of is:uance of the operating license, subject to the liminations and modifications listed in Section 50.55a(b) of 10 CFR Part 50.
A preservice inspection program based on the 1974 Edition through the Summer 1975 Addenda of Section XI of the ASME Code was submitted by the applicant in a letter dated March 15, 1978. We are currently reviewing the program and evaluating tb requests for relief from the ASME Code examination requirements for the La Salle Unit 1.
We are also evaluating the preservice inspection exemptions for Class 1 components as allowed by Paragraph lWB-1220(b)(1) of the ASME Code.
Our evaluation of the applicant's relief request with a supporting technical justification will be presented in a >upplement to the Safety Evaluation Report. The inservice inspection program will be evaluated after the applicable ASME Code Edition & Addenda have been determined and before tne initial inservice inspections are performed.
The conduct of periodic inspections and hydrostatic testing of pressure retaining components of the reactor coolant pressure boundary, in accordance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code and 10 CFR Part 50, will provide reasonable assurance that evidence of structural degradation or loss of leaktight integrity occurring during service will be detected in time to permit corrective action before the safety functions of a component are compromised.
Compliance with the preservice and inservice inspections required by this Code and 10 CFR Part 50 constitutes an acceptable basis for satisfying the inspection requirements of General Design Criterion 32.
~
. 6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS General Design Criterion 36, " Inspection of Emergency Core Cooling System;"
Criterion 39, " Inspection of Containment Heat Removal System;" Criterion 42,
" Inspection of Containment Atmosphere Cleanup Systems;" and Criterion 45,
" Inspection of Cooling Water System," Appendix A of 10 CFR Part 50 require, in part, that the subject system be designed to permit appropriate periodic inspection of important component parts to assure system integrity and capability.
Section 50.55a(g),10 CFR Part 50 defines the detailed requirements for the preservice and inservice inspection programs for light water cooled nuclear power facility components.
Based upon a construction permit date of September 10, 1973 this section of the Code of Federal Regulations requires that a preservice inspection program be developed for Class 2 components and be implemented using at'least the Edition and Addenda of Section XI of the ASME Code in effect six months prior to the date of issuance of the construction permit. Also, the initial inservice inspection program must comply with the requirements of the latest Edition and Addenda of Section XI of the ASME Code in effect 12 months prior to the date of issuance of the operating license, subject to the limitations and modifications listed in Section 50.55a(b) of 10 CFR Part 50.
A preservice inspection program based on the 1974 Edition through Summer 1975 Addenda of Section XI of the ASME Code was submitted by the applicant in a letter dated March 15, 1980. We are currently reviewing the program and evaluating the request for relief from the ASME Code examinations for La Salle Unit 1.
We are also evaluating the exemptions for Class 2 components due to low pressure and temperature and chemistry control, as permitted by lWC-1220(a) & IWC-1220(c) of the Code.
Our evaluation of the
. applicant's relief requests with a supporting technical justification will be provided in a supplement to the Safety Evaluation Report. The inservice inspection program will be evaluated after the applicable ASME Code Edition and Addenda have been determined and before the initial inservice inspection are performed.
Compliance with the preservice and inservice inspections required by the ASME Code and 10 CFR Part 50 constitutes an acceptable basis for satisfying applicable requirements of Genersl Design Criteria 36, 39, 42, and 45.