ML13330B325
| ML13330B325 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 05/31/1988 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Baskin K Southern California Edison Co |
| References | |
| TAC-59138 NUDOCS 8806200134 | |
| Download: ML13330B325 (10) | |
Text
May 31, 1988 Docket No. 50-206 DISTRIBUTION Docket Fie
-NRC & LPDRs CTrammell Mr. Kenneth P. Baskin GHolahan Vice President JLee Southern California Edison Company OGC-White Flint 2244 Walnut Grove Avenue PDV Plant File Post Office Box 800 EJordan Rosemead,.California 91770 JPartlow ACRS (10)
Dear Mr. Baskin:
ANolan NL-007 (EG&G)
RStevens
SUBJECT:
PLANT-SPECIFIC ATWS MITIGATION SYSTEM ACTUATION CIRCUITRY (TAC NO. 59138)
Re:
San Onofre Nuclear Generating Station, Unit No. 1 In reviewing your letters of January 29 and March 7, 1988 relating to the above subject, we have determined that the additional information identified in the enclosure is needed to continue our review. In order to maintain our review schedule, your response is requested within 60 days of your receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under Pub. L.96-511.
Please contact us if you should have any questions regarding this request.
Sincerely, original signed by Charles M. Trammell Charles M. Trammell, Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosure:
Request for Additional Information cc w/enclosure:
See next page D5 DR *.
5 mell:dr G i on 88
/\\/88 OFFICIAL RECORD COPY 8806200134 880531 PDR ADOCK 05000206 P
o UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
'lay 31, 1988 Docket No.
50-206 Mr. Kenneth P. Baskin Vice President Southern California Edison Company 2244 Walnut Grove Avenue Post Office Box 800 Rosemead, California 91770
Dear Mr. Baskin:
SUBJECT:
PLANT-SPECIFIC ATWS MITIGATION SYSTEM ACTUATION CIRCUITRY (TAC NO. 59138)
Re:
San Onofre Nuclear Generating Station, Unit No. 1 In reviewing your letters of January 29 and March 7, 1988 relating to the above subject, we have determined that the additional information identified in the enclosure is needed to continue our review. In order to maintain our review schedule, your response is requested within 60 days of your receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under Pub. L.96-511.
Please contact us if you should have any questions regarding this request.
Sincerely, Charles M. Trammell, Senior Project Manager Project Directorate V Division of Reactor Projects -
- III, IV, V and Special Projects
Enclosure:
Request for Additional Information cc w/enclosure:
See next page
Mr. Kenneth P. Baskin San Onofre Nuclear Generating Southern California Edison Company Station, Unit No. 1 cc Charles R. Kocher, Assistant Mr. Jack McGurk, Acting Chief General Counsel Radiological Health Branch James Beoletto, Esquire State Department of Health Southern California Edison Company Services Post Office Box 800 714 P Street, Office Bldg. 8 Rosemead, California 91770 Sacramento, California 95814 David R. Pigott Mr. Hans Kaspar, Executive Director Orrick, Herrington & Sutcliffe Marine Review Committee, Inc.
600 Montgomery Street 531 Encinitas Boulevard, Suite 105 San Francisco, California 94111 Encinitas, California 92024 Mr. Robert G. Lacy Mr. Dennis M. Smith, Chief Manager, Nuclear Radiological Programs Division San Diego Gas & Electric Company Governor's Office of Emergency Svcs.
P. 0. Box 1831 State of California San Diego, California 92112 2800 Meadowview Road Sacramento, California 95832 Resident Inspector/San Onofre NPS 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 Director Energy Facilities Siting Division Energy Resources Conservation &
Development Commission 1516 - 9th Street Sacramento, California 95814 Regional Administrator, Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, California 94596
ENCLOSURE SPN ONOFRE NUCLEAR GENERATION STATION, UNIT 1 COMPLIANCE WITH ATWS RULE 10 CFR 50.62 REQUEST FOR INFORMATION A. The following list of comments/questions were generated from a review of the licensee's submittal of January 29, 1988, covering the plant-specific AMSAC design.
- 1. General a) Under "BACKGROUND," reference is made to TMI upgrades of the auxiliary feedwater system. Have these upgrades been applied to AFW Train B? Describe what they consist of and how they are compatible with AMSAC requirements.
b) Describe the relationship between all the various AFW systems in use or planned for use at the station.
c) What are the setpoints for the steam generator low-low level trip for AFW-B? (Relate to requirements of WCAP-10858-P-A, Rev. 1) d) The submittal does not mention the SG blowdown and sample line isolation valves. Describe how these valves will be affected by the AMSAC. (Relate to requirements of WCAP-10858-P-A, Rev. 1) e) Section 5.0, Page 2-8, of WCAP-10858-P-A, Rev. 1, states that AMSAC shall provide a backup to the RPS. Describe how this is to be accomplished by using AFW Train B.
f) Section 11.0, Page 3-7, of WCAP-10855-P-A, Rev. 1 describes the required AMSAC time response. Describe how the AFW Train B time response compares to these time response requirements.
-2
- 2.
Diversity a) Describe the degree of diversity that exists between the Foxboro spec 200 equipment and the Foxboro Spec 200 Micro equipment. (Relate to the diversity requirements of WCAP 10858-P-A.)
b) Describe the degree of diversity that exists between the pressure transmitters (and associated current loop equipment) that are used in AFW Train B and the RPS.
c) Describe the degree of diversity that exists between the pressure transmitters (and associated current loop equipment) that are used in the AFW Train B and AFW Train A.
- 3. Logic Power Supply a) Provide details (including drawings) on the separation that exists between the RPS logic power supplies and AFW Train B logic power.
b) Can the P-7 signal be disabled by the manual reset when the signal is above 10% reactor power? Describe how the manual resets are to be controlled administratively.
c) The new Turbine Trip solenoid is a non-1E device. Describe the type of isolation used between this device and the Class 1E circuits with which it interfaces and discuss qualification per Appendix A of the NRC SER on WCAP 10858-P-A.
-3
- 4. Safety-Related Interface a) Describe the existing RPS applicable safety criteria and its documented location, i.e., FSAR, TS. Provide information to ensure that the RPS will continue to meet all existing applicable safety criteria subsequent to the installation and implementation of AMSAC.
b) Define all Class 1E to non-Class 1E interfaces for AMSAC and show their location on Attachment 1 to your January 29, 1988 submittal. Address qualification of the isolators in accordance with Appendix A to the NRC SER on WCAP-10858-P-A.
c) Expand on the DTT circuit qualification. Relate to the classification of AFW Train B (Class 1E) equipment.
- 5. Quality Assurance a) The submittal states that compliance to GL 85-06 is not required. Describe the QA that is being used, i.e., 10 CFR 50, Appendix B and relate to each specific criterion of GL 85-06.
- 6. Maintenance Bypass a) Section 14.0, Page 3-9, of WCAP-10858-P-A, Rev. 1 states that removal of one AMSAC SGLL input circuit should be accomplished by placing that.circuit in the tripped mode. Discuss how the SONGS-1 AMSAC design complies with this requirement.
b) Discuss the controls or procedures that are in effect when the entire AFW Train B is removed from service.
-4 c) Discuss the control room indication and annunciation of all bypasses as it relates to the AFW Train B safety function and the apparent parallel AMSAC function.
d) Expand on bypass of the DTT circuit for AFW testing purposes.
- 7. Operating Bypass a) What signals can inhibit or enable the P-7 and under what conditions? Compare the use of P-7 to the WCAP-10858-P-A (Rev. 1) recommendation for the use of the turbine impulse pressure signal permissive.
b) Describe any inhibits or enables associated with the AFW Train B logic circuits or actuation circuits. Provide logic drawings to support this information.
c) Are there other AFW Train B operating bypass and status indications that are not shown or discussed? If so, provide details.
d) Discuss the indication and annunciation of the AMSAC bypasses, i.e., location, annunciator window(s).
- 8. Means for Bypassing a) This section reflects the capability for the removal of individual input channels while the Maintenance Bypass section states that single channels cannot be placed in the tripped mode (requires removal of complete train).
Clarify this apparent difference and relate to the requirements of WCAP-10858-P-A, Rev. 1.
5 b) The WCAP specifically prohibits the use of certain methods for bypassing. Discuss why the disallowed methods for bypassing (lifting leads, etc.) are being used (relate to TMI/AFW upgrade) and provide justification for this deviation.
c) Describe the use and function of the permanently installed jacks to be implemented for testing. When are these jacks to be installed?
- 9. Manual Initiation a) Describe how the DTT will be manually initiated.
- 10. Electrical Independence a) Will the electrical isolators used in the AMSAC be diverse from the RPS?
(Describe how diversity will be obtained).
- 11.
Equipment Qualification (EQ) a) What is the EQ status of the DTT?
b) Discuss the EQ status of the parts of the AFW "B"/DTT that are not subjected to a harsh environment.
- 12.
Testability at Power a) Provide additional discussion related to the capability for testing the AMSAC during reactor operation.
b) State the planned at-power test frequencies.
-6 c) When are complete end-to-end tests to be performed, i.e.,
from sensor through to the final AMSAC actuation device?
d) Describe when and how the DTT circuits will be tested.
e) Discuss the control room indication during testing as related to AMSAC, i.e., "AMSAC DISABLED."
f) Discuss the control room annunciation scheme as related to AFW ECCS and AMSAC functions.
- 13.
Completion of Mitigative Actions a) Provide a description of how the mitigative action goes to completion upon AMSAC initiation.
b) Provide a description of the required reset of the plant systems actuated by the AMSAC.
- 14. Technical Specifications a) AFW Train B is a safety-related system. Describe how AFW Train B/AMSAC will be covered by the TS, LCOs, or emergency procedures.
b) It appears that the DTT circuitry is a safety-related system.
Describe the controlling procedures for the DTT system.
c) Describe what credit is taken for AFW Train B in the safety analysis.
d) Describe how the existing safety analysis will be affected by assigning AFW Train B to perform the AMSAC function.
B. The following list of comments/questions were generated from a review of the licensee's submittal of March 7, 1988, covering the qualification testing of the electrical isolation devices to be used in the plant-specific AMSAC design.
- 1. The submittal did not specify where in the AMSAC each type of isolation device was going to be used (between safety related and non-safety related portions). Provide information showing:
a) the interface locations and type of device at that location, and b) the specific Class 1E and non-Class 1E ports of the device.
- 2. Information was supplied showing that the maximum credible fault (MCF) voltage used in the testing of the isolators exceeded that to which the isolators could be exposed to in the AMSAC. Provide similar information with respect to the potential MCF current that could be associated with the MCF voltage.
- 3. It appears from the test report that the CCC relay Model 8N13 was not tested by applying the MCF voltage/current to the non-Class 1E side of the relay in the transverse mode while monitoring the Class 1E side of the relay for any perturbations. Provide summary test data to verify that the appropriate MCF tests were performed.
- 4. Provide test configuration schematics of the tests performed on the Model 8N13.
- 5. From the responses to Item 7, it appears that Class 1E power is being applied to the non-Class 1E side of an isolator (8N13).
Re-examine the isolator circuits and verify that Class 1E power is being applied to the Class 1E side of the isolator.