ML20203M559
| ML20203M559 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 04/24/1986 |
| From: | Nerses V Office of Nuclear Reactor Regulation |
| To: | Noonan V Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8605010574 | |
| Download: ML20203M559 (11) | |
Text
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APR 2 4 II66 Docket No.:
50-443 MEMORANDUM FOR:
Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR I.icensing-A FROM:
Victor Nerses, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A
SUBJECT:
SEABROOK SAFETY PARAMETER DISPLAY SYSTEM SITE AUDIT DATE & TIME:
May 20-22, 1986 LOCATION:
Information and Education Center Seabrook Site Seabrook, New Hampshire PURPOSE:
To perform an audit of the Seabrook Safety Parameter Display System (Refer to Agenda)
PARTICIPANTS:
NRC PSNH R. Eckenrode L. Walsh, et al.
V. Nerses, et al.
Victor Nerses, Project Manager PWR Project Directorate #5 Division of PWR t.icensing-A cc: See next page Note:
The NRC meeting is open to interested members of the public to attend as observers. Members of the public who wish to attend this meeting must contact V. Nerses (301) 492-8535 no later than May 19, 1986.
(The NRC generally does not have access authority to allow members of the public to attend the site audit portion of the meeting.
The authority resides with the PSNH who has responsibility to maintain physical security and proprietary information. Therefore, admission of the public to the Seabrook construction site is at the discretion of PSNP.
For further information about access to the site audit, contact the site representative, Mr. Sanchez, at (603) 474-9521, Extension 2453).
es 4/23/86 8605010574 860424 PDR ADOCK 05000443 A
MEETING NOTICE DISTRIBUTION 24 %
, Docket or Central File NRC Participants NRC PDR R. Eckenrode I.ocal PDR V. Nerses, et al.
PD#5 Readino File ORAS H. Denton Project Manager V. Nerses OELD E. Jordan B. Grimes J. Partlow (Emergency. Preparedness only)
Receptionist (Building where meeting is being held)
ACRS (10)
OPA N. Olson Resident Inspector Regional Administrator M. Rushbrook cc: Licensee / applicant & Service 1.ist 1
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Jg UNITED STATES
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p, NUCLEAR REGULATORY COMMISSION
'j WASHINGTON, D. C. 20555 O 2 4 L986 e,,,e Docket No.:
50-443 MEMORANDUM FOR:
Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR Licensing-A I
FROM:
Victor Nerses, Project Manager
. PWR Project Directorate #5 Division of PWR licensing-A
SUBJECT:
SEABROOK SAFETY PARAMETER DISPLAY SYSTEM SITE AUDIT DATE & TIME:
May 20-22, 1986 LOCATION:
Information and Education Center Seabrook Site Seabrook, New Hampshire DURPOSE:
To perform an audit of the Seabrook Safety Parameter Display System (Refer to Agenda)
PARTICIPANTS:
NRC PSNH R. Eckenrode L. Walsh, et al.
V. Nerses, et al.
Victor Nerses, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A s
I cc: See next page i
Note:
The NRC meeting is open to interested members of the public to attend as observers. Members of the public who wish to attend this meeting must contact V. Nerses (301) 492-8535 no later than i
May 19, 1986.
(The NRC generally does not have access authority to allow members of the public to attend the site audit 1
portion of the meeting. The authority resides with the PSNH who has responsibility to maintain physical security and proprietary information. Therefore, admission of the public to the Seabrook construction site is at the discretion of PSNH.
For further information about access to the site audit, contact the site representative, Mr. Sanchez, at (603) 474-9521, Extension 2453).
1
.Mr. Robert J. Harrison Public Service Company of New Hampshire Seabrook Nuclear Power Station cc:
Thomas Dignan, Esq.
E. Tupper Kinder, Esq.
John A. Ritscher, Esq.
G. Dana Bisbee, Esq.
Ropes and Gray Assistant Attorney General 225 Franklin Street Office of Attorney General Boston, Massachusetts 02110 208 State Fosue Annex Concord, New Hampshire 03301 Mr. Bruce B. Beckley, Project Manager Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station Manchester, New Hampshire 03105 c/o US Nuclear Regulatory Commission Post Office Box 700 Dr. Mauray Tye, President Seabrook, New Hampshire 03874 Sun Valley Association i
209 Sumer Street Mr. John DeVincentis, Director Haverhill, Massachusetts 01839 Engineering and licensing i
Yankee Atomic Electric Company Robert A. Backus, Esq.
1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 116 f.owell Street Manchester, New Hampshire 03105 Mr. A. M. Ebner, Project Manager United Engineers & Constructors William S. Jordan, III 30 South 17th Street Diane Curran Post Office Box 8223 Harmon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW Suite 430 Washington, D.C.
20009 Mr. Philip Ahrens, Esq.
Assistant Attorney General State Pouse, Station #6 Augusta, Maine 04333 Jo Ann Shotwell, Esq.
Office of the Assistant Attorney General Environmental Protection Division Mr. Warren Fall One Ashburton Place Public Service Company of Boston, Massachusetts 02108 New Hampshire Post Office Box 330 D. Pierre G. Cameron, Jr., Esq.
Seabrook, New Hampshire 03874 General Counsel Public Service Company of New Hampshire Seacoast Anti-Pollution league Post Office Box 330 Ms. Jane Doughty Manchester, New Hampshire 03105 5 Market Street Portsmouth, New Hampshire 03801 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Mr. Diant P. Randall 631 Park Avenue 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 Richard Fampe Esq.
New Hampshire Civil Defense Agency 107 Pleasant Street Concord, New Hampshire 03301
,Public Service Company of Seabrook Nuclear Power Station New Hampshire cc:
Mr. Calvin A. Canney, City Manager Mr. Alfred V. Sargent, City Fall Chairman 126 Daniel Street Board of Selectmen Portsmouth, New Hampshire 03301 Town of Salisbury, MA 01950 Ms. Letty Pett Senator Gordon J. Pumphrey Town of Brentwood ATTN: Tom Burack RFD Dalton Road U.S. Senate Brentwood, New Hampshire 03833 Washington, D.C.
20510 Ms. Roberta C. Pevear Mr. Owen B. Durgin, Chairman Town of Pampton Falls, New Hampshire Durham Board of Selectmen Drinkwater Road Town of Durham Hampton Falls, New Hampshire 03844 Durham, New Hampshire 03824 Ms. Sandra'Gavutis Charles Cross, Esq.
Town of Kensington, New Hampshire Shaines, Mardrigan and RDF 1 McEaschern East Kingston, New Hampshire 03827 25 Maplewood Avenue Post Office Box 366 Portsmouth, New Hampshire 03801 Chairman, Board of Selectmen RFD 2 South Hampton, New Hampshire 03827 Mr. Guy Chichester, Chaiman Rye Nuclear Intervention Mr. Angie Machiros, Chairman Committee Board of Selectmen c/o Rye Town Fall for the Town of Newbury 10 Central Road Newbury, Massachusetts 01950 Rye, New Hampshire 03870 Ms. Cashman, Chairman Jane Spector Board of Selectmen Federal Energy Regulatory Town of Amesbury Comission Town Hall 825 North Capital Street, NE Amesbury, Massachusetts 01913 Room 8105 Washington, D. C.
20426 Ponorable Peter J. Matthews Mayor, City of Newburyport Mr. R. Sweeney Office of the Mayor New Hampshire Yankee Division City Hall Public Service of New Hampshire Newburyport, Massachusetts 01950 Company 7910 Woodmont Avenue Mr. Donald E. Chick, Town Manager Bethesda, Maryland 20814 Town of Exeter j
10 Front Street Mr. William B. Derrickson Exeter, New Hampshire 03823 Senior Vice President Public Service Company of New Hampshire Post Office Box 700, Route 1 Seabrook, New Hampshire 03874
AUDIT PLAN FOR F
EVALUATION OF THE SEABROOK STATION SAFETY PARAMETER DISPLAY SYSTEM BACKGROUND All holders of operating licenses issued by the Nuclear Regulatory Commission (licensees) and applicants for an operating license (OL) must provide a Safety Parameter Display System (SPDS) in the control room of their plant.
The Commission approved requirements for the SPDS are defined in Supplement 1 to NUREG-0737.
The purpose of the.SPDS is to provide a concise display of critical plant variables to control room operators to aid them in rapidly and reliably determining the safety status of the plant.
NUREG-0737, Supplement 1, requires licensees and applicants to prepare a written safety analysis describing the basis on which the selected parameters are sufficient to assess the safety status of each identified function for a wide range of events, which include symptoms of severe accidents.
Licensees and applicants shall also prepare an implementation plan for the SPDS which contains schedules for design, development, installation, and full operation of the SPDS as well as a design verification and validation plan.
The safety analysis and the implementation plan are to be submitted to the NRC for staff review.
The results of the staff's review are to be published in a safety Evaluation Report (SER).
Section 18.2 of NUREG-0800, " Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," describes how the staff performs SPDS reviews for applicants of operating licenses.
The staff's review process will evaluate the (1) safety analysis report, (2) the implementation plan, and (3) the verification and validation (V&V) plan.
In addition three separate audit meeting / site visits, as described below, may be arranged through the Licensing Project Manager.
As dictated by the comprehensiveness of the applicant / licensee's
' documentation and the schedule for design ar.d implementation of the SPDS, the objectives of the audits may be met in fewer site visits.
Design Verification Audit:
The purpose of this audit meeting is to obtain additional information required to resolve any outstanding questions about the Verification and Validation Program, to confirm that the V&V Program is being correctly implemented, and to audit the results of the V&V activities to date.
At this meeting the applicant should provide a thorough description of the SPDS design process.
Emphasis should be placed on how the applicant is assuring that the implemented SPDS will:
provide appropriate parameters, be isolated from safety systems, provide reliable and valid data, and 1
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incorporate good hum:n factors engineering prcctica.
D'esign Validation Audit:
After review of all documentation, an audit may be conducted to review the as-built prototype or installed SPDS.
The purpose of this audit is to assure that the results of the applicant or licensee's testing demonstrate that the SPDS meets the functional requirements of the design and to assure that the SPDS exhibits good human factors engineering practice.
Installation Audit:
As necessary, a final audit may be conducted at the site to ascertain that the SPDS has been installed in accordance with the applicant / licensees plan and is functioning properly.
A specific concern is that the data displayed reflect the sensor signal which measures the variable displayed.
This audit will be coordinated with and may be conducted by the NRC Resident Inspector.
Based upon the advanced state of the design a combined Design Verification and Design Validation audit is planned for May 20-21, 1986.
1 NRC AUDIT TEAM The NRC Audit Team will consist of a representative from the PWR-A Electricel, Instrumentation and Control Systems Branch, assisted by two consultants from the Lawrence Livermore National
)
Laboratory (LLNL).
PSNH SUPPORT NJ2DED l
The following personnel should be available for discussions with the audit team:
The person having lead responsibility for SPDS design and implementation, Engineering and/or vendor staff familiar with all aspects of SPDS design and operation, Representatives of Operations, Maintenance and Training departments, Representatives of the software development team, Representatives of the System Verification and Validation
- team, Representatives of the human factors design / review staff, Plant operators designated as SPDS users.
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Mont of thera individuele nsed only be cvailtble to support specific audit activities discussed in the audit agenda.
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AGENDA l
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SEABROOK STATION l
SPDS AUDIT DAY 1:
8:30 A.M.
NRC entrance briefing and introductions.
8:40 A.M.
Overview of SPDS design program and current status by by PSNH including:
9# pt
- 8.. /
Boundaries of the SPDS with respect to the
~.
o plant computer, o
Human factors analysis, standards, and criteria used in the design process with emphasis on plant specific considerations, o
System reliability and availability:
Design characteristics to insure high availability, Methods used to estimate system availability, Methods planned to monitor operational availability.
o Data validation methodology used in the SPDS including data validation performed by any necessary supporting systems that provide validated data to the SPDS. (possible examples are RVLIS and radiation monitoring),
o Operator training in use of the SPDS, o
System maintenance philosophy and staffing.
10:30 A.M. Description of Verification and Validation (V&V)
Program including:
o Description of the VEV team and discussion of the degree of independence from the design
- team, o
Scope and depth of the V&V program, 4
,l
^
o Test cases for validation of SPDS paramaters j
and how they demonstrate the representativeness and useability of the selected parameters for evaluating transient conditions that do not fall within the plant design basis, o
Discussion of Emergency Response Guideline Validation Program and applicability to the Validation of the Seabrook Station SPDS, o
Verification of human factors aspects of
- system, o'
Coordination with other NUREG-0737 initiatives, with emphasis on control room design review (including a short discussion of SPDS related findings),
o Overview of SPDS V&V documentation.
2:30 P.M. NRC questions and review of V&V documentation.
As part of the V&V documentation review the audit team will want to select sample SPDS requirements and trace their implementation through hardware and software specifications, algorithms and integrated system performance.
The audit team will review documentation of verification and validation activities for each step.
To support this review all existing system documentation in the following categories should be available for the SPDS and for any necessary supporting systems that provide validated data to the SPDS.
o System functional requirements documents, o
Hardware and software specifications, o
Algorithm descriptions, and source code, o
Emergency operating procedures, o
System availability study, o
Data validation "setpoints",
o Software and hardware verification test procedures and results, o
System validation test procedures and
- results, 5
o System installation test procedures and
- results, t
o Documentation of independent verification reviews of functional requirements documents, hardware and software specifications, algorithms, test procedures and results, o
Drawings that document the make, type, and electrical connections to the SPDS electrical isolation devices.
This portion of the audit may extend beyond normal working hours.
PSNH's participation in the documentation review may be limited to one or two individuals who can answer most audit team questions about the system hardware, software, and the V&V process.
DAY 2:
8:30 A.M.
Identification of outstanding questions resulting from the V&V documentation review.
i 9:00 A.M. NRC human factors audit of displays, display formats, control devices, access and response times.
The audit team will wish to operate or witness operation of the system to access and examine all SPDS display formats.
This activity may be conducted in the Control Room, TSC, EOF, Control Room Simulator, or SPDS engineering simulator.
12:30 P.M.
Short tour of the control room including examination of the control room SPDS consoles and electrical isolation devices.
1:30 P.M. Walk-through of a plant-specific scenario that involves confirmation of containment isolation, i
monitoring of reactor building radiation levels and hydrogen concentration, transition from j
injection to recirculation cooling, and trends and monitoring of gaseous releases. PSNH should develop this scenario.
The scenario should be 1
walked-talked-through by an operator that has been familiarized with SPDS operation.
Upgraded emergency operating procedures should be used for I
the walk-through.
2:30 P.M. Discussion of outstanding questions.
3:30 P.M.
NRC audit team caucus.
4:00 P.M.
Exit briefing.
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