ML20154P330

Forwards Request for Addl Info Re 860106 SPDS Submittal. Onsite Preimplementation Audit Will Be Required to Complete Evaluation.Addl Info Requested by 860318

ML20154P330
Person / Time
Site:	Seabrook
Issue date:	03/11/1986
From:	Nerses V Office of Nuclear Reactor Regulation
To:	Harrison R PUBLIC SERVICE CO. OF NEW HAMPSHIRE
References
NUDOCS 8603200268
Download: ML20154P330 (9)

Text

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MAR 111986 Docket Nos.: 50-443 and 50-444 Mr. Robert J. Harrison President & Chief Executive Officer Public Service Company of New Hampshire Post Office Box 330 Manchester, New Hampshire 03105

Dear Mr. Harrison:

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Subject:

Request for Additional Information Concerning the Safety Parameter Display System for Seabrook Station The staff has reviewed your submittal of January 6, 1986 concerning the Safety Parameter Display System and concluded that insufficient information was provided to complete our evaluation. The information needed by the staff to continue the evaluation is defined in the enclosure. I request that you provide me your response by March 18, 1986. If this is not possible, please notify me.

An on-site pre-implementation audit will be required to complete the evaluation, and I expect that this audit will be accomplished within approximately one month following receipt of the additional information requested above.

Sincerely, Victor Nerses, Project Manager PWR Project Directorate No. 5 Division of PWR Licensing-A

Enclosure:

As stated cc: See next page DISTRIBUTION Docket'F,1]e; Rossi NRC"PDR BStevens LPDR EJordan JPartlow VNerses PWR5 Reading Attorney, ELD BGrimes MRushbrook VNoonan s N an 3//f /86 3 /86 8603200268 860311 PDR ADOCK 05000443 A PDR

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% , , , , ,.* MAR 11916 1 Docket Nos.: 50-443 and 50-444 Mr. Robert J. Harrison President & Chief Executive Officer Public Service Company of New Hampshire Post Office Box 330 Manchester, New Hampshire 03105

Subject:

Request for Additional Information Concerning the Safety Parameter Display System for Seabrook Station The staff has reviewed your submittal of January 6,1986 concerning the Safety Parameter Display System and concluded that insufficient information was provided to complete our evaluation. The infonnation needed by the staff to continue the evaluation is defined in the enclosure. I request that you provide me your response by March 18, 1986. If this is not possible, please notify me..

An on-site pre-implementation audit will be required to complete the evaluation, and I expect that this audit will be accomplished within approximately one month following receipt of the additional information requested above.

Sincerely, V ctor Nerses, Project Manager PWR Project Directorate No. 5 Division of PWR Licensing-A

Enclosure:

As stated cc: See next page

i . .

1 Mr. Robert J. Harrison

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i Public Service Company of New Hampshire Seabrrok Nuclear Power Station

! cc:

) Thomas Dignan, Esq. E. Tupper Kinder, Esq.

John A. Ritscher, Esq. G. Dana Bisbee, Esq.

l Ropes and Gray Assistant Attorney General 225 Franklin Street Office of Attorney General I

Boston, Massachusetts 02110 208 State House Annex Concord New Hampshire

Mr. Bruce Beckley, Project Manager j Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station j Manchester, New Hampshire 03105 t

c/o U.S. Nuclear Regulatory Comm.

Post Office Box 700 Dr. Murray Tye, President Seabrook, New Hampshire 03874 Sun Valley Association 209 Sunner Street Mr. John DeVincentis, Director

Haverhill, Massachusetts 08139 Engineering and licensing l Yankee Atomic Electric Company

! Robert A. Backus, Esq. 1671 Worchester Road

. O'Neil, Backus and Spielman Framingham, Massachusetts 01701 1 116 lowell Street '

l Manchester, New Hampshire 03105 Mr. A.M. Ebner, Project Manager United Engineers & Constructors Mr. Phillip Ahrens, Esq. 30 South 17th Street Assistant Attorney General Post Office Box 8223 l' State House, Station #6 Philadelphia, Pennsylvania 19101 Augusta, Maine 04333 William S. Jordan. III Mr. Warren Hall Diane Curran

, Public Service Company of Hannon, Weiss & Jordan i

New Hampshire 20001 S. street, NW j Post Office Box 300 Suite 430 l

Seabrook, New Hampshire 03874 Washington, D.C. 20009 Seacoast Anti-Pollution league Jo Ann Shotwell, Esq.

Ms. Jane Doughty Office of the Assistant Attorney 5 Market Street General Portsmouth, New Hampshire 03801 Environmental Protection Division i

One Ashburton Place .

i Ms. Diana P. Randall Boston, Massachusetts 02108

! 70 Collins Street

) Seabrook, New Hampshire 03874 D. Pierre G. Cameron, Jr. , Esq.

General Counsel Richard Hampe, Esq. Public Service Company of New New Hampshire Civil Defense Agency Hampshire 107 Pleasant Street Post Office Box 330 Concord, New Hampshire 03301 Manchester, New Hampshire 03105 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue

King of Prussia, Pennsylvania 19406 I,., __, - . . _ _ _ . . - _ _ . . - . . . , _ . _ . . - , , . , , - . - _ - - . _ _ _ _ . . . , _ . - . . . - . . _ _ . . . . - . - - - . ,.,_--.__,..m.. -

Public Service Con:pany of Seabrook Nuclear Power Station New Hampshire CC:

Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Hall Chairman 126 Daniel Street Board of Selectmen Portsmouth, New Hampshire 03801 Town of Salisbury, MA 01950 Ms. I.etty Hett Senator Gordon J. Humphrey Town of Brentwood ATTN: Tom Burack RFD Dalton Road U. S. Senate Brentwood, New Hampshire Washington, D.C. 20510

)

Ms. Roberta C. Pevear Town of Hampton Falls, New Hampshire Drinkwater Road Hampto9 Falls, New Hampshire 03844

) Ms. Sandra Gavutis Mr. Owen B. Durgin. Chairman Town of Kensington, New Hampshire Durham Board of Selectmen RDF 1 Town of Durham

• East Kingston, New Hampshire 03827 Durham, New Hampshire 03824 j Ms. Anne Verga Chairman, Board of Selectmen Charles Cross, Esq.

Town Hall Shaines, Mardrigan and South Hampton, New Hampshire 03827 McEaschern l . 25 Maplewood Avenue Mr. Angie Machiros, Chairman Post Office Box 366 Board of Selectmen Portsmouth, New Hampshire 03801

, for the Town of Newbury Newbury, Massachusetts 01950 Mr. Guy Chichester, Chairman Rye Nuclear Intervention Comittee Ms. Rosemary Cashman, Chairman c/o Rye Town Hall i Board of Selectmen 10 Central Road Town of Amesbury Rye, New Hampshire 03870 1

Town Hall Amesbury, Massachusetts 01913 Jane Spector Federal Energy Regulatory Honorable Richard E. Sullivan Comission l Mayor, City of Newburyport 825 North Capitol Street, N.E.

Office of the Mayor Room 8105 City Hall Washington, D.C. 20426 Newburyport, Massachusetts 01950 Nr. R. Sweeney Mr. Donald E. Chick, Town Manager New Hamphire Yankee Division Town of Exeter Public Service Company of New 10 Front Street Hampshire

, Exeter, New Hampshire 03823 7910 Woodmont Avenue l Bethesda, Maryland 20814

! Mr. William B. Derrickson l'

Senior Vice President Public Service Company of

New Hampshire Post Office Box 700, Route 1 i Seabrook, New Hampshire 03874 i

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. . Enclosure t

REQUEST FOR ADDITIONAL INFORMATION CONCERNING THE SEABROOK STATION 4

SAFETY PARAMtitM DISPLAY SYSTEM Each operating reactor shall be provided with a Safety Parameter Display l System (SPDS). The Commission approved requirements for an SPDS are defined

in NUREG-0737, Supplement 1. In the Regional workshops on Generic Letter 82-33 t

held during March 1983, the NRC discussed these requirements and the staff's 1

review of the SPDS.

4 The staff reviewed the SPDS safety analysis provided by Public Service of New Hampshire dated January 6, 1986 (Reference 1). The staff was unable to complete l

the review because of insufficient information. The following additional in-formation is required to continue the review:

Isolation Devices Provide the following:

a. For the type of device used to accomplish electrical isolation, describe i

the specific testing performed to demonstrate that the device is accept-able for its application (s). This description should include elementary diagrams when necessary to indicate the test configuration and how the maximum credible faults were applied to the devices.

b. Data to verify that the maximum credible faults applied during the test were the maximum voltage / current to which the device could be exposed,

and defkne how the maximum voltage / current was determined.

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c. Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e., open and short circuits).

l d. Define the pass / fail acceptance criteria for each type of device.

e. Provide a commitment that the isolation devices comply with the environ-ment qualifications (10CFR 50.49) and with the seismic qualifications which were the basis for plant licensing.

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f. Provide a description of the measures taken to protect the safety systems from electrical interference (i.e., Electrostatic Coupling, EMI, Common Mode and Crosstalk) that may be generated by the SPDS.

g. Provide information to verify that the Class IE isolation is powered from a Class IE source.

Human Factors Engineering

a. Human Factors Program Provide a description of the display system, its human factored design, and the, methods used and results from a human factors program to ensure that the displayed information can be readily perceived and comprehended so as not to mislead the operator.

b. Data Validation Describe method used to validate data displayed on the SPDS and how

" conservative substitute values" are calculated. Also describe how

" conservative substitute values" are made known to the operator.

c. Verification and Validation Program The SPDS report describes the validation prograr for the Westinghouse Own-er's Group (WOG) Emergency Response Guidelines (ERGS). It does not describe the Verification and Validation Program used in the development of the SPDS. This program needs to be described alor.1 with a description of re'sults to date and the corrective actions taken to address identified design deficiencies.

d. Unreviewed Safety Questions Provide conclusions regarding unreviewed safety questions or changes to technical specifications,

e. Implementation Plan Provide a schedule for full implementation of the SPDS including hardware, software, operator training, procedures and user manuals.

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-4 Paremeter Selection As a result of its review, the staff noted that the following variables are not proposed for the Seabrook SPDS:

1. RHR Flow ,

2. Steam Generator (or steamline) Radiation

3. Stack Monitor

4. Containment Isolation

5. Containment Hydrogen Concentration During RHR and ECCS modes of cooling when steam gerierators are notva'ailable, RHR flow is a key indicator to monitor the viability of the heat removal

, system.

Steamline (or steam generator) radiation, in con,iunction with containment radiation and reactor stack radiation, gives a rapid assessment of radiation status for the most likely radioactive release paths to accomplish the " Radio-activity Control" safety function. For a rapid assessment of Radioactivity control, the applicant has not demonstrated how radiation in the secondary system (steam generators and steamlines) is monitored by SPDS when the steam generators and/or their steamlines are isolated. The analysis should be ex-panded to include this discussion, f6j$;n ,

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Containment isolation is an important parameter for use in making a rapid assessment of " Containment Conditions." In particular, a determination that known process pathways through containment have been secured provides significant additional assurance of containment integrity.

Containment hydrogen concentration is a key parameter used in the emergency guidelines to monitor combustible gas control and to indicate a compromise of the " Containment Conditions" safety function.

The above variables do, for given scenarios, provide unique inputs to the

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detenninations of status for their respective Critical Safety Functions (CSFs),

which have not been discussed by the applicant as being satisfied by other variables in the proposed Seabrook SPDS list. The applicant should address these variables and their functions by: (1) adding the variables to the Seabrook SPDS, (2) providing alternate added variables along with justifications that these alternates accomplish the same safety functions for all scenarios, or (3) providing justification that variables currently on the Seabrook SPDS do in fact accomplish the same safety functions for all scenarios.

Reference Letter to V..Noonan from J. DeVincentes, SBN-920, dated January 6,1986, "NUREG-0737 Task I.D.2, Plant Safety Parameter Display Console."

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