ML20203J097
| ML20203J097 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 07/31/1986 |
| From: | George Thomas PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.31, TASK-TM GL-83-35, SBN-1175, NUDOCS 8608050180 | |
| Download: ML20203J097 (5) | |
Text
.
d George S. Thomas Vice President-Nuclear Production Pubuc Service of New Hampshire N;w Hampshire Yankee Division July 31, 1986 SBN-1175 T.F.
B7.1. 2 United States Nuclear Regulatory Commission Washington, DC 20555 Attention:
Mr. Vincent S. Noonan, Project Director PWR Project Directorate No. 5
References:
(a) Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Letter dated November 2,1983, " Clarification of TMI Action Plan Item II.K.3.31 (Generic Letter No.
83-35)", from D. G. Eisenhut (c) USNRC Letter dated June 11,1985, "TMI Action Item II.K.3.30 for Westinghouse Plants", G. W. Knighton to R. J. Harrison (d) WOG Letter (OG-190), dated June 11, 1986, " Westinghouse Owners Group Transmittal of WCAP-11145", L. D. Butterfield to J. Lyons Subj ect :
TMI Action Plan Item II.K.3.31; Plant Specific Calculations to Show Compliance with 10CFR50.46
Dear Sir:
In References (b) and (c), the Staff indicated that the resolution of TMI Action Plan Item II.K.3.31 may be accomplished by generic analyses to demonstrate that the previous NRC approved WFLASH SBLOCA EM results were conservative when compared with the new NOTRUMP SBLOCA EM.
In response to the above, generic studies were undertaken by the Westinghouse Owners Group (WOG) of which we are a participating member.
The WOG has completed these generic studies and has submitted the results of the analyses to the NRC in the topical report WCAP-11145 [ Reference (d)]. The purpose of this letter is to inform you that Seabrook Station is referencing topical report WCAP-11145 in order to satisfy the require-ments of TMI Action Item II.K.3.31 for Seabrook Station, in a generic fashion, in accordance with References (b) and (c).
8608050180 860731 PDR ADOCK 05000443 A
- PDR, P.O. Box 300. Seabrook, NH 03874. Telephone (603) 474-9574 fI
m.
a
,p i
United States Nuclear Regulatory Commission SBN-Il75 Attention:
Mr. Vincent S. Noonan Page 2 i
Topical report WCAP-11145 documents the results of a series of Spall Break LOCA (SLLOCA) analyses performed with the NRC approved E
NOTRUMP SBLOCA Evaluation Model. Cold leg break spectrum analyses were performed for the limiting SBLOCA plant from each of the West-inghouse 4-loop, 4-loop Upper Head Injection (UHI), 3-loop, and 2-loop plant categories. The limiting SBLOCA plant in each category was de-fined on the basis of previous SBLOCA analyses which were performed with the NRC approved WFLASH SBLOCA EM.
In addition to the cold leg break spectrums, a hot leg and pump suction break were performed as pa'r t of the 4-loop plant analyses, confirming that the cold leg was still the worst break location. Comparison of the NGTRUMP cold leg break spectrum results with the previously generated WFLASH results, fi showed that the WFLASH results were conservative for all plant cate-t gories.
In particular, the 4-loop plant category results showed that
+
the NOTRUMP SBLOCA EM calculated a limiting Peak Clad Temperature (PCT) which was 537'F lower than that previously calculated by the the WFLASH SBLOCA EM.
In this regard, it should also be noted that we reviewed the generic WCAP-11145 and have determined that the 4-loop category is
' representative of Seabrook Station's configuration and design charac-teristics.
The generic results documented in WCAP-11145, demonstrate that a
' '~ lant specific reanalysis of the 4-loop Seabrook Station plant with the p
NOTRUMP SBLOCA EM would result in the calculation of a limiting PCT
' which would be significantly lower than the 1790*F PCT currently calcu-lated with the WFLASH SBLOCA EM.
Hence, the WFLASH SBLOCA EM results, which currently form the licensing basis for Seabrook Station, are con-servative and still valid for demonstrating the adequacy of the Emer-gency Core Cooling System to mitigate the consequences of a SBLOCA, as required by 10CFR50.46. Therefore, it is concluded that a plant specific analysis is not needed for Seabrook Station.
Rather, we reference WCAP-11145 to comply with TMI Action Item II.K.3.31 on a generic basis, i
in accordance with References (b) and (c).
Purs uant to the above, enclosed please find a revision to the re-sponse for the above referenced TMI Action Item provided in FSAR Section 1.9.
This revised response will be incorporated into the FSAR by a future amendment.
We trust this information is acceptable and request the status of these items be reflected in the next supplement to Seabrook's SER.
Very truly yours,
Ge e
Thomas Enclosure Atonic Safety and Licensing Board Service List cc:
Dicus Curren, E:quir3 Pater J. Mathews, Mayor H:rmon & Weico City Hall 2001 S. Street, N.W.
Newburyport, MA 01950 Suite 430 Washington, D.C.
20009 Judith H. Hizner Silvergate, Gertner, Baker, Sherwin E. Turk, Esq.
Fine, Good & Mizner Office of the Executive Legal Director 88 Broad Street U.S. Naclear Regulatory Commission Boston, MA 02110 Tenth Floor Washington, DC 20555 Calvin A. Canney City Manager Robert A. Backus, Esquire City Hall 116 Lowell Street 126 Daniel Street P.O. Box 516 Portsmouth, NH 03801 Manchester, NH 03105 l
Stephen E. Herrill, Esquire l
Philip Ahrens. Esquire Attorney General Assistant Attorney General George Dana Bisbee, Esquire Department of The Attorney General Assistant Attorney General Statehouse Station #6 Office of the Attorney General Augusta, ME 04333 25 Capitol Street Concord, NH 03301-6397 Mrs. Sandra Gavutis Chairman, Board of Selectmen Mr. J. P. Nadeau RFD 1 - Box 1154 Selectmen's Office Kenosington, NH 03S27 10 Central Road Rye, NH 03870 Carol S. Sneider, Esquire Assistant Attorney General Mr. Angie 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 Mr. William S. Lord U.S. Senate Board of Selectmen Washington, DC 20510 Town Hall - Friend Street (ATIN: Tom Burack)
Amesbury, MA 01913 Richard A. Hampe, Esq.
Senator Gordon J. Humphrey Hampe and McNicholas 1 Pillsbury Street 35 Pleasant Street Concord, NH 03301 Concord, NH 03301 (ATTN: Herb Boynton)
Thomas F. Powers, III H. Joseph Flynn, Esquire Town Manager Office of General Counsel Town of Exeter Federal Emergency Management Agency 10 Front Street 500 C Street, SW Exeter, NH 03833 washington, DC 20472 Brentwood Board of Selectmen Paul McEachern, Esquire RFD Dalton Road Matthew T. Brock, Esquire Brentwood, NH 03833 Shaines & McEachern 25 Maplewood Avenue Gary W. Holmes, Esq.
P.O. Box 360 Holmes & Ells Portsmouth, NH 03801 47 Winnacunnet Road Hampton, NH 03842 Robert Carrigg Town Office Mr. Ed Thomas Atlantic Avenue FEMA Region I North Hampton, NH 03862 442 John W. McCormack PO & Courthouse Boston, MA 02109
Enclosure to SSN-1175 SB 1 & 2 Ausndment 56 FSAR November 1985
]
i Task II.K.3.31 Plant Specific Calculations to Show Compliance with 10 CFR, Part 50.46 (NUREG-0737)
Plant-specific calculations using NRC-approved models for small break Loss-Of-Coolant Accidents (LOCAs) as described in Item II.K.3.30 to show compliance with 10 CFR 50.46 should be submitted for NRC approval by all licensees.
Response
0:: :x,-____ :: "'" :.".;; L.. L _ ::.".2.2^. IVMM
- k Task III.A.1.1 Upgrade Licensee Emergency Preparadness - Short Term (NUREG-0660)
Position:
Licensees will upgrade emergency preparadness in accordance with the requirements described in the NRC " Action Plan for Promptly Improving Emergency Preparedness" (SECY 79-450), which was distributed to all licensees during regional meetings in August, 1979, and in accordance with subsequently issued criteria (NUREG-0654).
Response
Refer to the Seabrook Station Radiological Emergency Plan.
Task III.A.1.2 Upgrade Emergency Support Facilities Position:
Each operating nuclear power plant shall maintain an on-site Technical Support Center (TSC) separate from, and in close proximity to, the control l
room that has the capability to display and transmit plant status to those I
individuals who are knowledgeable of, and responsible for, engineering and l
management support of reactor operations in the event of an accident. The center shall be habitable to the same degree as the Control Room for l
postulated accident conditions. The licensee shall revise his emergency l
plans, as necessary, to incorporate the role and location of the TSC.
Records that pertain to the as-built conditions and layout of structures, systems, and components shall be readily available to personnel in the TSC.
An Operational Support Center (OSC) shall be established separate from the control room and other emergency response facilities as a place where operations support personnel can assemble and report in an emergency I
situation to receive instructions from the station staff. Communications l
shall be provided between the OSC, TSC, EOF, and Control Room.
l 1.9-31
Enclosure to SBN-1175 (Conti nued)
Insert "A" onto page 1.9-31
Response
As provided in PSNH Letter (SBN-1175) dated July 31, 1986, Seabrook Station hereby references WCAP-11145 which demonstrates, generically, the plant's compliance with 10CFR50.46. This completes TMI Action Item II.K.3.31 for Seabrook Station.
l l