ML20052F868
| ML20052F868 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/23/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20052F866 | List: |
| References | |
| NUDOCS 8205140065 | |
| Download: ML20052F868 (2) | |
Text
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- %o NUCLEAR REGULATORY COMMISSION j
. 1 W ASHINGTON, D. C. 20555 a,
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 42 TO FACILITY OPERATING LICENSE N0. DPR-7_0_
PUBLIC SERVICE ELECTRIC AND GAS' COMPANY, PHILADELPHIA ELECTRIC COMPANY, DELMARVA POWER AND LIGHT COMPANY, AND ATLANTIC CITY ELECTRIC COMPANY SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 DOCKET N0. 50-272 Introduction By letter dated March 13, 1982, Public Service Electric and Gas Company (the licensee) requested a Technical Specifications change for Salem Unit 1 pertaining to the steam generator channel head cladding inspection. The change requested relates to paragraph 4.4.10.1.2 which presently reads:
4.4.10.1.2 Augmented Inservice Inspection Program for Steam Generator Channel Heads - The steam generator channel heads shall be ultrasonic inspected during each of the first three refueling outages using the same ultrasonic inspection procedures and equipment used to generate the base-line data.
These inservice ultrasonic inspecticns shall verify that the cracks observed in the stainless steel cladding prior to operation have not propagated into the base material. The stainless steel clad surfaces of the steam generator channel heads shall also be 100% visually inspected during the above outages and a television camera shall be used to make a videotape recording of the condition of this cladding.
Each videotape shall be compared with those obtained during the previous outages to determine that the cladding does not show any abnormal degradation.
The proposed revision is as follows:
4.4.10.1.2 Augmented Inservice Inspection Program for Steam Generator Channel Heads - The steam generator channel heads shall be ultrasonically inspected during each of the first three refueling outages using the same ultrasonic inspection procedures and equipment used to generate the baseline data. These inservice ultrasonic inspections shall verify that the cracks observed in the stainless steel cladding prior to operation have not propa-gated into the base material. The stainless steel clad surfaces of the steam generator channel heads shall also be visually inspected ;, ring the above outages. This may be accomplished by direct visual examination or by remote means such as television camera.
If the visual examination, either direct or remote, reveals detectable cladding indications, a record shall be made by means of a video tape recording or photographs for comparison purposes.
8205140065 820423 PDR ADOCK 05000 P
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- Background A remotely operated video scanning system was developed spec'.fically to provide a means of visually examining the interior clad surfaces of the Salem steam generator channel heads as a supplement to ultrasonic examination from the exterior surfaces.
Remote video scanning was proposed as an alternate to direct visual examination to minimize radiation exposure to inspection personnel.
Experience at Salem Unit No.1 during the first two refueling outages has demonstrated to the contrary; more exposure was incurred in setting up, adjusting and removing the equipment than would have been incurred by a simple direct visual examination.
Furthermore, cracking known to exist in the cladding surface as determined by dye penetraat examination has not been detectable so far by either direct or remote visual examination; thus negating the value of, and need for, a videotape record.
Evaluation Visual examination of the steam generator channel heads by remote means is an impractical requirement to impose when assessed against the safety gained and dose consideration. The purposes for remote visual examination were to reduce personnel exposure to radiation and to provide records of cladding condition for comparison with the results of the next examination.
Experience with remote examination equipment set up has shown that personnel exposure to radiation increases when compared to the exposure received during a direct visual examination.
The staff has determined that the request does not cause a significant change
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in the effectiveness of the examination or the purposes of the original Technical Specification.
The request will accomplish the results desired while reducing personnel exposure to radiation. We, therefore, approve the use of either visual or television methods of inspections.
Environmental Consideration We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact.
Having made this determination, we have further concluded that the amendment involves an action which is insignificant i
from the standpoint of environmental impact and, pursuant to 10 C.FR 551.5(d)(4),
that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the proba-bility or consequences of accidents previously considered and does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Date:
April 23, 1982 Principal Contributors: George Johnson, Materials Engineering Branch
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