ML20054B212
| ML20054B212 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/07/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Dietch R SOUTHERN CALIFORNIA EDISON CO. |
| References | |
| LSO5-82-04-016, LSO5-82-4-16, NUDOCS 8204160405 | |
| Download: ML20054B212 (4) | |
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April 7,1982 DISTRIBUTION Docket NRC PDR Local PDR Docket No. 50-206 ORB Reading LS0S-82-04-016 NSIC DCrutchfield HSmith WPaul son y h 1S'!f,O Mr. R. Dietch Vice President ACRS (10)
Nuclear Engineering and Operations SEPB f k /f 9 Southern California Edison Company TIppolito o 2244 Walnut Grove Avenue
$y, g p7 Post Office Box 800 g
g Rosemead, California 91770 g
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Dear Mr. Dietch:
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SUBJECT:
STEAM LINE BREAK INSIDE/0UTSIDE CONTAINMENT - SAN ONOFRE NUCLEAR GENERATING STATION UNIT NO. 1 i
We have reviewed your submittal dated February 2,1982 that forwarded the San Onofre Unit 1 emergency operating procedures.
In addition, we discussed our concerns regarding safe shutdown following a postulated steam line break with your representatives in a meeting on March 2,1982.
Based on our review of your submittal and the March 2,1982 meeting, we find that the information described in the enclosure is required to i
complete our review.
To facilitate the completion of our review prior to restart from your current outage, please provide your response by April 30, 1982. Since this request is being sent only to Southern California Edison Company and relates to an approval request by Southern California Edison Company concerning an issue specific to San Onofre Unit 1, no clearance from the Office of Management and Budget (OMB) is required.
p/
i Sincerely.
Original signed by N
cs 6 (/oS )
gu Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page IT su"
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8204160405 820407 PDR ADOCK 05000206 p
G0HC FORM 318 (10-80) NRCM 024o OFFICIAL RECORD C.OPY usc.m i
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s Mr. R. Dietch April 7,1982 cc Charles R. Kocher, Assistant General Counsel James Beoletto, Esquire Southern California Edison Company Post Office Box 800 Rosemead, California 91770
' David.R. Pigott Orrick, Herrington & Sutcliffe 600 Montgomery Street San Francisco, California 94111
- Harry B. Stoehr San Diego Gas & Electric Company P. O. Box 1831 San Diego, California 92112 Resident Inspector / San Onofre NPS c/o U. S. NRC P. O. Box 4329 San Clemente, California 92672 Mayor City of San Clemente San Clemente, California 92672 Chairman Board of Supervisors County of San Diego San Diego, California 92101 California Department of Health ATTN:
Chief, Environmental Radiation Control Unit Radiological Health Section 714 P Street, Room 498 Sacramento, California 95814 U. S. Environmental Protection Agency c.
Region IX Office ATTN:
Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 Robert H. Engelken, Regional Administrator Nuclear Regulatory Commi'ssion, Region V 1450 tiaria Lane Walnut Creek, California 94596 E
ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION SAN ON0FRE UNIT NO. 1 DOCKET NO. 50-206 Upgrade of Emergency Operating Procedures 1.
Revise your emergency operating procedures to provide improvement for recognition of. system voids and methods for their control and eventual removal.
2.
In section A of the procedures, assure that instructions to re-pressurize -
(e.g., item 4.1.9) by initiation of safety injection o' charging will not r
cause a pressurized thermal shock to the vessel. Additionally, supply the analysis that supports the procedures in section C to show that termination of safety injection (e.g., item 4.5.1) would take place at primary system pressures that do not threaten the integrity of the vessel and that the HPI termination criteria are not mutually exclusive and can be achieved following a steam line break.*
3.
Revise your emergency operating procedures to provide improvement of instructions for alerting the operator to steam generator tube rupture of increased leakage that may occur following a steam line break.
4.
The steam line break procedures should provide clear references throughout to alternative procedures or methods for decay heat removal in the event feedwater is unavailab.le.
In particular, instructions should be provided for how to initiate " feed and bleed" decay heat removal. These instructions should address systems needed to be started, reset etc., in order to.get PORV operability, charging pump operability, etc.
5.
Provide the revised procedures for NRC staff review.
Analysis of Feed and Bleed Capability 6.
Provide the NRC staff with an analysis of the feed and blegd capability l
demonstrati.ng that:
a.
Charging capacity is sufficient for decay heat removal b.
PORV capacity is sufficient to depressurize the plant.
If not, and feed and bleed is done' at high pressure, show why pressurized thermal shock (cold charging water being added to the vessel at high pressure) is not a
- problem, c.
The operator has sufficient time to diagnose the event and initiate feed and bleed prior to core uncovery.
- Procedural changes that may result from this' evaluation in the short term, are not intended to supersede changes that may result from the ongoing generic review on thermal shock.
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J Operator Training 7.
Confirm that the operators have been thoroughly instructed in the revised procedures and the safety concern which prompted the revisions.
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