ML20195B326
| ML20195B326 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 05/27/1986 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.05, TASK-TM SBN-1068, NUDOCS 8605290211 | |
| Download: ML20195B326 (4) | |
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O SEABROOK STATION Engineering Of fice PutAc Service of New Hampshho New Hompshiro Yonkee Division May 27, 1986 SBN-1068 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 Permita CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 (b) USNRC Letter, dated May 20, 1986, V. Nerses to R. J. Harrison
Subject:
Reactor Coolant Pu Trip: TMI Action Itema II.K.3.5
Dear Sir:
As requested by the Staff, we have reviewed the enclosure to Reference (b) which documented the Staff's understanding of our telephone conversation on April 10, 1986. We agree with the enclosure except for two items. The corrections to these items are provided herewith.
We believe that the enclosed and Reference (h) completen our response to the above referenced TMI Action item and request that this he reflected in the next supplement to Seabrook's SER.
Very truly yours, A/nl John DeVincentia Director of Engineering Enclosure cc Atomic Safety and Licensing Board Service List 8605290211 860527 PDR ADOCK 00000443 hu I
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l P O Bcs 300
- Sectwook. NH 03874. Totophone (603)474-9521
Diano Curran, Esquire Calvin A. Cann:g Harmon & Weiss City Manager 2001 8. Street, N.W.
City Hall Suite 430 126 Daniel Stredt Portsmouth, NH 03801 Washington, D.C.
20009 Shemin E. Turk Esq.
Stephen E. Merrill, Esquire Office of the Executive Legal Director Attorney General U.S. Nuclear Regulatory Coassission George Dana Bisbee, Esquire Tenth Floor Assistant Attorney General Washington, DC 20555 office of the Attorney Ceneral 25 Capitol Street Robert A. Backus, Require Concord, NH 03301-4397 116 Lowell Street F.O. Box 516 Mr. J. P. Nadeau Manchester, NH 03105 Selectmen's office 10 Centesi Road Philip Ahrens Esquire Rye, NH 03870 Assistant Attorney General Department of The Attorney General Mr. Angle Machiros Statehouse station M Chairman of the Board of Selectmen hugusta NE 04333 Town of Newbury Newbury MA 01950 Mrs. Sandra Cavutis Chairman, Board of selectmen Mr. Willian 3. Lord RF0 1 - Box 1154 Board of Selectmen Kennsington, NH 03827 Town Hall - Friend Street Amesbury, MA 01913 Carol S. Sneider, Esquire Assistant Attorney General Senator Cordon J. Humphrey Department of the Attorney General 1 Pillsbury Street One Ashburton Place, 19th Floor Concord, NH 03301 Boston, MA 02108 (ATTN: Herb Boynton)
Senator Gordon J. Humphrey N. Joseph Flynn, Esquire U.S. Senate Office of General Counsel i
Washington, DC 20510 Federal Beersency Management Agencyg (ATTN: Tom Burack) 500 C Street, SW Washington, DC 20472 Richard A. Hampe. Esq.
Hampe and McNicholas Paul McEacherm. Esquire 35 Pleasant Street Matthew T. Brock, Esquire Concord, NH 03301 Shatnes & McEachern 25 Maplewood Avenue Donald E. Chick P.O. Box 360 Town Manager Portsmouth, NH 03801 Town of Exeter
~
10 Front Street Cary W. Holmes, Esq.
Exeter NH 03833 Holmes & Elle 47 Winnscunnet Road Brentwood Board of Selectmen Hampton, NH 03841 RFD Dalton Road Brentwood, NH 03833 Mr. Ed Thomas FEMA Region !
Peter J. Mathews, Mayor 442 John W. McCormack PO & Courthouse City Hall Boston, MA 02109 Newburyport, MA 01950 Stanley W. Knowles, Chaiman Board of Selectmen P.O. Box 710 North Hampton, NH 03862 l
SBN-1068 s.
4.
Conditions outside of containment that may influence uncertainty are not addressed.
For example, has Seabrook surveyed the wiring and connections between the transmitters and the control room to assure that such accidents as a steam line break outside of containment will not introduce problems with readings in the control room, and have such considerations been factored into the uncertainty evaluation?
5.
The uncertainty determinations are stated to be based upon RTDs.
The core exit T/Cs are stated to be the basis for the determination of RCP trip.
Please explain the apparent discrepency.
(See Item A1. )
Applicant Response.
Information pertinent to each of the above items is as follows:
9 1.
The generic WOG Guidelines are used for containment conditions.
An adverse containment condition is considered to exist if a High-1 containment isolation signal is generated (4.3 psig) or if the integrated radiation dose in containment is greater than 1.4 X 10 Rads.
2.
Narrow range pressurizer pressure is the only applicable instrument with a transmitter inside containment.
This instrument will not be used in determining subcooling margin since it i: n:t ;r! icd t;
%,,cti.
.. 2 - 'r: m,,t.
The selected subcooling margin is sufficiently high that uncertainty variations due to an adverse containment condition are covered.
The same is true with the uncertainty of instrumentation other than that automatically used in the subcooling monitor.
In some cases, the uncertainty of instrumentation utilized in determination of the subcooling margin applicable to RCP trip is higher than would be the kC $, f G ffVre. JOuld bt"OokSidc. f d u "I a C.O P 5
N imbwt muge_ ama coa not 6e. med cu. a.cde-ton O RCP w g e
s
SBN-1068 Staff Evaluation. Determination and use of RCS subcooling as an RCP trip parameter is stated to have been performed in accordance with the generic guidance provided in the Revision 1 version of the Westinghouse Owners Group Emergency Response Guidelines.
Please relate this to the information which the staff reviewed and generically approved in Generic Letter 85-12 (Ref. 2).
For example, discuss comparisons between Seabrook and the Westinghouse Owners Group (WOG) generic information provided in response to Generic Letter 83-10 (Ref. 3), which was re'erenced in Reference 2.
The str** needs sufficient information regarding the uncertainty of the computer code results used in performance of analyses that it can formulate conclusions in regard to initial plant condition assumptions, and the major contributors to uncertainty. Where bases are w
upon generic accident and transient calculations, the staff needs to understand if there are any Seabrook specific features which affect the determinations and, if so, what equipment is involved and what is the impact upon the results.
Applicant Response. All of the information identified by the staff is contained in the referenced WOG documentation.
This can be condensed and provided to the staff if desired, and will be the duplicate of what has been provided by many other utilities in response to this staff question.
m;g; mum pech" v*lueA M36 The a.act i,t k a applicable to the Seabrook plant are @ psig for RCS pressure, 58 F for subcooling, and 685 psi for pressure difference from the RCS to the SG secondary side.
There are no unique Seabrook plant features that affect the generic WOG information.
Additional Staff Comment.
The staff briefly identified the pertinent points in the referenced WOG documentation on which there may have been a question, and the applicant was obviously familar with the information.
There is no need for the applicant to " rubber stamp" the information onto an additional response for staff review.
The above provided additional plant specific information is sufficient.
B.
Potential Reactor Coolant Pump Problems 9
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