ML13317A230

Forwards Request for Addl Info Concerning SEP Topics III-4.C Re Internally Generated Missiles & IX-1 Re Fuel Storage.Response Requested within 30 Days

ML13317A230
Person / Time
Site:	San Onofre
Issue date:	07/16/1982
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Dietch R Southern California Edison Co
References
TASK-03-04.C, TASK-09-01, TASK-3-4.C, TASK-9-1, TASK-RR LSO5-82-07-042, LSO5-82-7-42, NUDOCS 8207200209
Download: ML13317A230 (4)

Text

July 16, 1982 Docket No. 50-206 LS05 07-042 Mr. R. Dietch, Vice President Nuclear Engineering and Operations Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770

SUBJECT:

SEP TOPICS III-4.C, INTERNALLY GENERATED MISSILES AND IX-l, FUEL STORAGE - REQUEST FOR ADDITIONAL INFORMATION SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 By letter dated April 29, 1982, you submitted topic assessments on the above topics. The staff has reviewed your assessments and has deter mined that the information requested in the enclosures is needed in order for us to complete our review. Your response is requested with in 30 days of receipt of this letter.

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, 0MB clearance kis not atgliO ddunder P.L.96-511.

Sincerely, Origirl signed7 y Dennis M. Crutchfield, Chief t oo)

Operating Reactors Branch No. 5 Division of Licensing ADD:

Enclosures:

As stated 64 cc w/enclosures:

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NRC FORM 318 (1m0 NRM 0240 OFFICIAL RECORD COPY usaeo: eai-as-sea

Mr. R. Dietch San Onofre Unit 1

-R D Docket No. 50-206 Revised 3/30/82 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. 0. Box 1831 San Diego, California 92112 Resident Inspector/San Onofre NPS c/o U. S. NRC P. 0. 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 Region IX Office ATTN:

Regional Radiation Representative 215 Freemont Street San Francisco, California 94111 Robert H. Engelken, Regional Administrator Nuclear Regulatory Commission, Region V 1450 Maria Lane Walnut Creek, California 94596 SYSTEMATIC EVALUATION PROGRAM REQUEST FOR ADDITIONAL INFORMATION SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 TOPIC:

III-4.C, Internally Generated Missiles

1. Standard Review Plan 3.2.2 identifies a list of fluid systems important to safety. The following systems from this list were not explicitly addressed in your evaluation. For each system, either discuss what other systems provide that safety function and where such systems are evaluated in the topic assessment or provide an evaluation of the system with respect to Topic III-4.C.

a. Steam Generator Blowdown System

b. Containment Cooling System

c. Combustible Gas Control System

d. Spent Fuel Pool Cooling and Cleanup System

e. Emergency Diesel Engine Cooling Water System

f. Emergency Diesel Engine Starting System

g. Emergency Diesel Engine Lubricating System

h. Emergency Diesel Engine Combustion Air Intake and Exhaust System

2. Provide an evaluation of potential missiles which could be ejected from the reactor coolant pump motor.

3. Provide an evaluation of the effects of missile generation along the CVCS letdown line inside containment.

4. Discuss applicable valve design aspects which preclude missile generation of valve stems, bonnet ejection and unrestrained valve operators.

5. Provide an evaluation of the missile protection afforded to electrical and instrumentation cables required for systems important to safety. Identify vulnerable cables and associated systems which could suffer-degradation upon cable severence.

SYSTEMATIC EVALUATION PROGRAM REQUEST FOR ADDITIONAL INFORMATION SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 TOPIC:

IX-1, Fuel Storage

1. The licensee is requested to verify that a Keff equal to or less than 0.98 will be maintained with new fuel of the highest anticipated reactiv ity assuming optimum moderation, for example, foam, spray, small droplets or mist.

Include any information regarding the new fuel storage facility which would prevent inadvertent flooding (e.g., covers, dratns, etc.)

2. The licensee is requested to verify that spent fuel storage racks are designed such that a fuel assembly cannot be.inserted anywhere other than in a design location.

3. The licensee is requested to verify that for the spent fuel pool a Keff equal to or less than 0.95 will be maintained when the storage racks are fully loaded and flooded with non-borated water.

4. The licensee stated in his submittal dated April 29, 1982 that the spent fuel pool temperature would be maintained below 120'F. The licensee did not indicate use of Branch Technical Position (BTP) ASB 9-2 for calculating the decay heat -loads. Consequently, we are not sure how much conservatism is in the licensee's analysis. Therefore, provide the followinq information with the heat exchangers expetted fouling factor and pluggage factor for the life of the plant:

a. Maximum normal heat load and the pool temperature with the maximum normal heat load using the heat load based on BTP ASB 9-2;

b. Maximum normal heat load and the pool temperature with the maximum normal heat load using the heat based on BTP ASB 9-2 and the-:worst single active failure. Provide a discussion of the failure and the operation of the remaining portion of the system;

c. Maximum abnormal heat load and pool temperature resulting from a full core off-load 30 days following a refueling off-load (pool should be considered filled) using the BTP ASB 9-2; and

d. Given a loss of all spent fuel pool cooling provide the time to pool boiling for the -maximum heat load and for the maximum abnormal heat load.