ML20137R058
| ML20137R058 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 02/05/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| SBN-940, NUDOCS 8602070172 | |
| Download: ML20137R058 (7) | |
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UI SEABROOK STATION Engineering Office Pubic Service of New Hampshke February 5, 1986 Now Hampshire Yonkee Division SBN-940 T.F. B7.1.3 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
Reference:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) Westinghouse Electric Corporation letter (NS-EPR-2895),
dated March 14,1984, "Special Rod Tests," E. P. Rahe, Jr.
to C. H. Berlinger
Subject:
Seabrook Startup Test Program
Dear Sir:
Recently, members of your staff requested clarification of the review / approval process in our startup test program. More specifically, in our discussions, your staff questioned our review / approval process with respect to programs used by other applicants.
To clarify our program, startup test results at Seabrook will undergo a three step review process. The initial review will be performed by the individual test director, who will insure that all required analyses have been performed, that the acceptance criteria have been met and/or that additional action is undertaken to resolve discrepancies. When this review is completed, the entire test package will receive a secondary review by the reactor startup supervisor and by the test group manager (Phn ses 2-6).
After all testing is completed for a given plateau, the reactor startup supervisor and the test group manager (Phases 2-6) will present the results to the Station Operations Review Committee (SORC) for final review and approval. The power level will not be escalated until SORC approval is obtained.
All analyses associated with a given plateau will be completed prior to escalating to the next plateau with the exception of those tests that are listed on the attached Table A-1, which is part of our Startup Test Procedure 1-ST-1.
The tests indicated in Table A-1 will undergo a preliminary anelysis and review by the reactor startup supervisor, the test group manager (Phase 2-6) and SORC as described in the above paragraph. The attached table
-indicates those specific tests and the maximum power levels allowed prior to completion of the analyses, review and final SORC approval. This assures that our program does not allow prior escalation without thorough and extensive review of test results.
48!
P.O Box 300 Soobrook.NH 03874. Tofophone (603)474-9521 8602070172 060205 ff; PDR ADOCK 05000443
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United States Nuclear Regulatory Commission Attention:
Mr. Vincent S. Noonan Page 2 The attached Table A-1 also reflects the deletion of the Negative Rate
' Trip Test described in FSAR Table 14.2-5 (Sheet 35). The justification for the deletion of this test is provided in Reference (b). This change to Table 14.2-5 (i.e., see Attachment 1) will be incorporated into the FSAR by a i
future amendment.
l Should you or your. staff have any questions, please do not hesitate to contact us.
We do request that the acceptability of this test deletion be reflected in the next supplement to Seabrook Station's SER.
Very truly yours, i
bh John DeVincentis, Director Engineering and Licensing Enclosure cc: Atomic Safety and Licensing Board Service List I
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William S..Torden, III Donald E. Chick Diane Curran Town Manager Harmon, Weiss & Jordan Town of Exeter 20001 S. Street, N.W.
10 Front Street Suite 430 Exeter, NH 03833 Washington, D.C.
20009 Brentwood Board of Selectmen Robert G. Perlis RED Dalton Road Office of the Executive Legal Director Brentwood, NH 03833 U.S. Nuclear Regulatory Commission Washington, DC 20555 Richard E. Sullivan, Mayor City Hall Robert A. Backus, Esquire Newburyport, MA 01950 116 Lowell Street P.O. Box 516 Calvin A. Canney Manchester, NH 03105 City Manager City Hall Philip Ahrens, Esquire 126 Daniel Street Assistant Attorney General Portsmouth, NH 03801 Augusta, ME 04333 Dana Bisbee, Esquire Mr. John B. Tanzer Assistant Attorney General Designated Representative of Office of the Attorney General the Town of Hampton 208 State House Annex 5 Morningside Drive Concord, NH 03301 Hampton, NH 03842 Anne Verge, Chairperson Roberta C. Pevear Board of Selectmen Designated Representative of Town Hall the Town of Hampton Falls South Hampton, NH 03827 Drinkwater Road Hampton Falls, NH 03844 Patrick J. McKeon Selectmen's Office Mrs. Sandra Gavutis 10 Central Road Designated Representative of Rye, NH 03870 the Town of Kensington RFD 1 Carole F. Kagan, Esquire East Kingston, NH 03827 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Jo Ann Shotwell, Esquire Washington, DC 20555 Assistant Attorney General Environmental Protection Bureau Mr. Angi Machiros Department of the Attorney General Chairman of the Board of Selectmen One Ashburton Place, 19th Floor Town of Newbury Boston, MA 02108 Newbury, MA 01950 Senator Gordon J. Humphrey Town Manager's Office U.S. Senate Town Hall - Friend Street Washington, DC 20510 Amesbury, MA 01913 (ATTN: Tom Burack)
Senator Gordon J. Humphrey Diana P. Randall.
1 Pillsbury Street 70 Collins Street Concord, NH 03301 Seabrook, NH 03874 (ATTN: Herb Boynton)
H. Joseph Flynn Office of General Counsel Federal Emergency Management Agency 500 C Street, SW Washington, DC 20472
SBN-940 TABLE A-1 Test Analysis Schedule Exceptions Test Results Test Required Prior Test Procedure To Exceeding Test Description Performed At Number 5%
RCS Flow Measurement Hot Standby 1-ST-11 50%
Boron Endpoint HZP l-ST-17 Measurement Control Bank Worth HZP 1-ST-20 Flux Map (Low Power)
HZP l-ST-19 Power Coefficient 30%
l-ST-30 75%
RCS Flow Coastdown Hot Standby 1-ST-12 Pseudo Rod Ejection HZP 1-ST-21 Load Swing 30%, 50%
l-ST-34 Power Coefficient 50%
l-ST-30 Flux Map (Rod Drop)
-50%
l-ST-31 90%
Rod Drop Test 50%
l-ST-31 Test Power Coefficient 75%
l-ST-30 Load Swing 75%
l-ST-34 Large Load Reduction 75%
l-ST-35
l SBN-940 f
FSAR Table 14.2-5 Revisions Seabrook Station I
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Awoa w.m+
1 SB 1&2 Amendment 48 FSAR January 1983 i
TABLE 14.2-5 (Sheet 2 of 53)
Index Title Sheet 22.
Natural Circulation Test 25 23.
Dynamic Automatic Steam Dump control 26 24.
Automatic Reactor Control 27 25.
Automatic Steam Generator Level Control 28 26.
Thermal Power Measurement and Statepoint Data Collection 29 27.
Startup Adjustments of Reactor Control System 30 28.
Calibration of Steam and Feedwater Flow Instrumentation 31 29.
Core Performance Evaluation 32 30.
Power Coef ficient Measurement 33 1
31.
Static Rod Drop aad Flux Asymmetry Evaluation 34 32.(NeMve hTriph
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33.
Shutdown from Outside the Control Room 36 34.
Load Swing Test 37 35.
Large Load Reduction Test 38 36.
Axial Flux Dif ference Instrumentation Calibration 39 37.
Steam Generator Moisture Carryover Measurement 40 38.
Unit Trip from 100 Percent Power 41 39.
Station Blackout Test 42 40.
NSSS Acceptance Test 43 41.
Radiation Survey 44 42.
Water Chemistry Control 45
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43.
Process Computer 46 I
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M SB 1 & 2 FSAR TABLE 14.2-5 (Sheet 35 of 53) 32.
NEG IVE RATE TRIP TEST Objective To demonstrate o ration of the negative rate trip cire try and to monitor plant response fo owing a trip from 50% reactor powe Plant Condi tions/Pr requisites The plant will be at le at the 50% power plat u.
Test Method Two RCCA's, selected bas d on their loc ion and worth as the most diffi-cult to detect, will be opped causi a negative rate trip of the Reactor Protection System. The p1 nt respo during the trip will be monitored.
The drop time of a selecte RCCA w' I also be monitored.
Acceptance Criteria The following criteria wil e utilized to determine acceptability:
1.
The reactor shd 1 hav tripped as a result of a negative rate trip.
2.
All full,. ength RCCA's s 11 be released and shall have bottomest.
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3.
The ressurizer safety valv s shall not have lifted.
4.
'e steam generator safety va ves shall not have lifted.
5 Safety injection was not initi ed.
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