ML15223A681
| ML15223A681 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/12/1980 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 8012020807 | |
| Download: ML15223A681 (6) | |
Text
NOVEMBER 1 2 1980 DISTRIB.U.T1..N.
JRoe its NSIC RTedesco L PDr ORB#4 Rdg TNovak Dockets Nosk 269, 50-270 GLainas and 50-287 RReid NRR Rdg MFairtile DEisenhut RIngram RPurple.
HOrnstein
.Mr. William 0. Parker, Jr.
EBlackwood Vice President - Steam Producti&gpiBenedetto Duke Power Company IE-3 P. 0. Box 2178 ACRS-16 422 South Church Street OELD Charlotte, North Carolina 2824 EOD r,
0 Gray File
Dear Mr. Parker:
By letter dated August 18, 1980 you submitted the information requested by the NRC letter of December 20, 1979 regardihg the safety grade upgrade of the existing control grade anticipatory reactor trips (ART) at the Oconee Nuclear Station, Units Nos. 1, 2 and 3. Attachment 1.of your August 18 letter provided an environmental test report on the pressure switches used in the safety grade circuits.
In order to complete our review of the environmental qualifications of these switches, we need the enclosed additional information, NUREG-0737, "Clarification of TMI Action Plan Requiremetits", dated October 31, 1980, in Appendix B provides applicable guidance in Criterion (1) for the environmental qualification of the ART system, and the applicability of Regulatory Guide 1.89 (NUREG 0588). You should not delay installation of the switches pending the result of our environmental qualification.review.
Kindly submit the requested information within 30 days of receipt of this letter.
Sincerely, Originl3 signed bY Robert W. Reid Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional Information cc w/enclosure: See next page 8o12o2oo7.
- See previous yellow for concurrences_
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Docket File-3 TERA-3 JRoe NRC PDR NSIC RReid L PDR ORB#4 Rdg MFairtile NRR Rdg RIngram Dockets Nos. 50-269, 50-270 DEisenhut HOrnstein and 50;' 287RPurple.
EBlackwood RTedesco PDiBenedetto TNovak IE-3 GLainas ACRS-16 Mr. William 0. Parker, Jr.
OELD Vice President - Steam Production AEOD Duke Power Company Gray File P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. PArker:
By letter dated Apgust 18, 1980 you submitted the information requested by the NRC letter of December 20, 1979 regarding the safety grade upgrade of the existing control grade anticipatory reactor trips at the Oconee Nuclear Station, Units Nos.,2 and 3. Attachment 1 of your August 18 letter provided an environmental test report on the pressure switches used in the safety grade circuits. In order to complete our review of the environmental qualifications of these switches, we need the enclosed addi tional information. You should not delay installation of the switches pending the result of our environmental qualification review.
Kindly submit the requested information within ten days of receipt of this letter.,
Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional Information cc w/encflosure:
See next page ORB#4:DL EQBDE DD-T OFFICEO
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 November 12, 1980 Dockets Nos. 50-269, 50-270 and 50-287 Mr. William 0. Parker, Jr.
Vice President -
Steam Production Duke Power Company P. 0. Box 2178 422 South Church Street Charlotte, North Carolina 28242
Dear Mr. Parker:
By letter dated August 18, 1980 you submitted the information requested by the NRC letter of December 20, 1979 regarding the safety grade upgrade of the existing control grade anticipatory reactor trips (ART) at the Oconee Nuclear Station, Units Nos. 1, 2 and 3. Attachment 1 of your August 18 letter provided an environmental test report on the pressure switches used in the safety grade circuits.
In order to complete our review of the environmental qualifications of these switches, we need the enclosed additional information. NUREG-0737, "Clarification of TMI Action Plan Requirements", dated October 31, 1980, in Appendix B provides applicable guidance in Criterion (1) for the environmental qualification of the ART system, and the applicability of Regulatory Guide 1.89 (NUREG 0588). You should not delay installation of the switches pending the result of our environmental qualification review.
Kindly submit the requested information within 30 days of receipt of this letter.
Sincerely, R'obert W. Reid, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
Request for Additional.
Information cc w/enclosure:
See next page
Duke Power Company cc w/enclosure(s):
Mr. William L. Porter Duke Power Company P. 0. Box 2178 422 South Church Street Office of Intergovernmental Relations Charlotte, North Carolina 28242 116 West Jones Street Raleigh, North Carolina 27603 Oconee Public Library 201 South Spring Street Walhalla, South Carolina 29691 Honorable James M. Phinney County Supervisor of Oconee County Walhalla, South Carolina 29621 Director, Criteria and Standards Division Office of Radiation Programs (ANR-460)
U. S. Environmental Protection Agency Washington, D. C. 20460 U. S. Environmental Protection Agency Region IV Office ATTN:
EIS COORDINATOR 345 Courtland Street, N.E.
Atlanta, Georgia 30308 Mr. Francis Jape U.S. Nuclear Regulatory Commission P. 0. Box 7 Seneca, South Carolina 29678 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Manager, LIS NUS Corporation 2536 Countryside Boulevard Clearwater, Florida 33515 J. Michael McGarry, III, Esq.
DeBevoise & Liberman 1200 17th Street, N.W.
Washington, D. C. 20036
OCONEE NUCLEAR STATION Enclosure ANTICIPATORY REACTOR TRIP REQUEST FOR ADDITIONAL INFORMATION If the environmentiof the pressure switches is as defined in Section 4.3.3 of to IE Bulletin 79-OB attached, you need respond only to Question 1 below; otherwise, respond to all the pertinent questions. For additional guidance refer to Supplement 2 of Bulletin 79-01B, response to Question 14 on harsh environ ment outside containment.
- 1. Provide the installation locations and the environmental bounding conditions for each (thermal ranges/transients, radiation, seismic).
- 2. Room temperature is listed in both tests. Please define in *F.
- 3. The test report indicates that the units were tested at several temperatures after being allowed to stabilize at each for one hour, excluding the possible detrimental effects of transients. Please justify.
- 4. Two switches were tested at temperatures of -30*F, 0*F and room temperature (700F?) and a third model was tested at -300F, room temperature (700F?) and 1600F. Explain the bases for these differences.
- 5. Only one model (646GZE5) was subjected to mechanical wear aging, with this testing performed at 2000F. Justify why only.one switch was subjected to this test and how the test temperature of 200aF was selected.
.6. Electrical contact chatter is represented by Figures 1 thru 4. More legible copies of these plots are required and should include a full description of the parameter being monitored on the vertical scale. In addition, provide a discussion of the effects this chatter would have on operability during and/or following seismic excitation.
- 7.
Provide a test response spectrum used for the seismic testing.
- 8. Provide the rate at which the vibration scan was performed in terms of octaves/minute.
- 9. Operability of the switches was not demonstrated during seismic excitation, provide the basis for this omission.
IL.
9 Attachment
- 2. Radiation - Due to differences in equipment arrangement within these areas and the significant effect of this factor on doses, radiation service conditions must be evaluated on a case by case.
basis. In general, a dose of at least 4 x 106 RADS would be expected.
- 3.
Submergence -
Not applicable.
- 4. Chemical Sprays - Not applicable.
4.3.3 Areas Normally Maintained at Room Conditions Class IE equipment located in these areas does not experience significant stress due to a change-in service conditions during a design basis event.
This equipment was designed and installed using standard engineering practices and industry codes and standards (e.g., ANSI, NEMA, Nattonal
- Electric. Code). Based on these factors, failures of equipment in these areas during a design basis event are expected to be random except to the extent that they may be due to aging or failures of air conditioning or ventilation systems.
Therefore, no special consideration need be given to the environmental qualification of Class IE equipment in these areas provided the aging requirements discussed in Section 7.0 below are satisfied and the areas are maintained at room conditions by redundant air conditioning or ventilation systems served by the onsite emergency electrical power system.
Equipment located in areas not served by redundant systems powered from onsite emergency sources should be qualified for the environmental extremes which could result from a failure of the systems as determined from a plant specific analysis.
5.0 QUALIFICATION METHODS