ML20040H415
| ML20040H415 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 02/09/1982 |
| From: | Haynes J SOUTHERN CALIFORNIA EDISON CO. |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20040H416 | List: |
| References | |
| REF-SSINS-6820 IEB-81-01, IEB-81-1, NUDOCS 8202180228 | |
| Download: ML20040H415 (3) | |
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Bulletin Reply Docket No'. 50-206 Southern California Edison Company W6 P. O. B O X 800 2 2 44 W ALNUT GHOVE AVENUE ROSEMEAD. CALIFORNI A 91770 J. G. H AY NES TELEPHONE February 9, 1982 g 2in 372 ira:
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Um Mr. R. H. Engelken Q
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Region V 1450 Maria Lane, Suite 260
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Dear Mr. Engelken:
DOCKET No. 50-206 SAN ON0FRE - UNIT 1 On January 27, 1981, you forwarded a copy of IE Culletin 81-01 requesting inspection and testing of mechanica' snubbers. We ind1cated in our February 27, 1981 letter that we would inspect all mechanical snubbers on safety-related systems prior to return to power from the outage.
We completed our inspection of testing which revealed two inoperable snubbers as reported in a Licensee Event Report 81-003 dated April 21, 1981 and further detailed in our June 3,1981 submittal.
In that letter we indicated the results of our inspections.
During a recent visit to our site, an inspector indicated he was not satisfied with the completeness of our response to the subject bulletin.
This letter provides further clarification and corpletes our response to IE Bu.letin 81-01.
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Responses to actions to be taken by Licensees of Operating Reactors is as follows:
Actions 1 and 2 required examination and testing of all International Nuclear Safeguards Corporation snubbers.
In our February 27, 1981 letter, we indicated that we do not have any snubbers made by this manufact ure r.
Action 3 required an inspection program covering snubbers produced by other manufacturers.
As indicated in our June 3,1981 letter and in Licensee Event Report 81-003, these inspections resulted in the reporting of two snubbers as inoperable.
A description of the visual examination and tests as required by Action 4a may be found in the enclosed procedure and test results.
In accordance with Action 4b requiring a report of our inspection results, we submit the following summary:
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Mr. R. H. Engelken - February 9, 1982 MECHANICAL SNUBBERS INSTALLED ON SAFETY-HELATED SYSTEMS '
-INACCESSIBLE DURING NORMAL PLANT OPERATION:
SNUBBER NO.
MODEL N0.
LOCATION SIZE (lbs.).
t 6000 1-SS-1501R-11.
PSA 3 S.I. - Piping System.
'1 1-SS-1501R-14 PSA 3 S.I. Piping System 6000 4
1-SS-1501R-12 PSA 3 S.I.- Piping System 6000 1-SS-15CIR-15 PSA 3 S.I. Piping System-6000 1-SS-1501R-10 PSA 3 S.I. Piping System
-6000 1-SS-1501R-13 PSA 3 S.I. Piping System 6000 1-6018-SS-006 PSA 3 S.I. Piping System 6000 1-6019-SS-006 PSA 3 S.I. Piping System 6000 734-S S-003 PSA I S.I. Piping System 1500 ACCESSIBLE DURING NORMAL PLANT OPERATION:
SNUBBER N0.
MODEL NO.
LOCATION SIZE (lbs._)
2-SC-1501R-03 PSA 35 S.I. Piping System 50,000 6-SC-1501R-02 PSA 35 50,000 SA-16-1 PSA 3
- .1 D/G Intake 6000 SA-16-2 PSA 3
- 1 D/G Intake 6000 P
SA-16-3 PSA 35
- 1 D/G Exhaust 50,000' F
SA-16-4' PSA 10 15,000 SA-16-5
'PSA 35 50,000 SA-16-6 PSA 10 15,000 SA-17-1 PSA 3
- 2 D/G Intake 6000 SA-17-2 PSA 3
- 2 D/G Intake 6000 SA-17-3 PSA 35
- 2D/G Exhaust 50,000 SA-17-4 PSA 10 15,000
' SA-17-5 PSA 35 50,000 SA-17-6 PSA 10-15,000 SA-1 PSA 1
- S.I. Piping System 1500 5-SS-151R-11 PSA 35 S.I. Piping System 50,000 14-PS-2A PSA 35 50,000
- 5-318-SW-10 PSA 3
S. I. Piping System 6000
- 5-318-SW-11 PSA 10 15,000 1-6019-SS-2 PSA 10 S.I. Piping System 15,004 6-SW-151R-15 PSA 10 15,000 14-PS-2B PSA 35 10,000
- These snubber were found inoperable and were reported in LER 81-003.
All of these snubbers are nanufactured by Pacific Scientific Company. These were -visually inspected for damage and manually tested to verify freedom of movement over the range of stroke in both compression and l
tension directions.
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Mr. R.1H.:Engelken February 9,-1982 Our response to action 4c was included in our June 3,1981 letter.
.This. report includes results of inspection of all" mechanical snubbers on safety-related systems.
Should you require additional ~information, please contact me.
Sincerel,
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L..F. Miller (NRC' Resident Inspector -fSan Onofre Unit 1)
Director, Of fice of Inspection and Enforcement Director, Office of Management Information and Program Control Director, Nuclear Safety Analysis Center J. Horner, Inspector, 0IE, Region V
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