ML20197F228

Notification of 860513-15 Instrumentation & Control Sys Site Audit.Electrical,Instrumentation & Control Sys Branch Site Audit Agenda Encl

ML20197F228
Person / Time
Site:	Seabrook
Issue date:	05/06/1986
From:	Nerses V Office of Nuclear Reactor Regulation
To:	Noonan V Office of Nuclear Reactor Regulation
References
NUDOCS 8605150493
Download: ML20197F228 (13)

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Docket No.: 50-443 MEMORANDUM FOR: Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR 1.icensing-A FROM: Victor Nerses, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A

SUBJECT:

SEABROOK INSTRUMENTATION & CONTROL SYSTEM SITE AUDIT DATE & TIME: May 13-15, 1986 (Exit meeting at 2:00 p.m. on May 15, 1986)

LOCATION: Information and Education Center -

Seabrook Site Seabrook, New Hampshire PURPOSE: To perform an audit of the Seabrook Instrumentation

& Control System (Refer to enclosed Agenda)

PARTICIPANTS: NRC PSNP R. Stevens, J. Mauck W. Fadden V. Nerses, et al. W. Reed, et al.

Victor Nerses, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A cc: See next page Note: The exit meeting is open to interested members of the public to attend as observers. Members of the public who wish to attend this meeting 1986. (must The NRCcontact V. Nerses generally (301) does not have492-8535 no latertothan access authority May 12, 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 secu'ity 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).

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Docket No.: 50-443 MEMORANDUM FOR: Vincent S. Noonan, Director PWR Project Directorate #5 Division of PWR t.icensing-A FROM: Victor Nerses, Project Manager PWR Project Directorate #5 Division of PWR I.icensing-A

SUBJECT:

SEABROOK INSTRUMENTATION & CONTROL SYSTEM SITE AUDIT DATE & TIME: May 13-15, 1986 (Exit meeting at 2:00 p.m. on May 15, 1986)

LOCATION: Information and Education Center Seabrook Site Seabrook, New Hampshire PURPOSE: To perfom an audit of the Seabrook Instrumentation

& Control System (Refer to enclosed Agenda)

PARTICIPANTS: NRC PSNP R. Stevens, J. Mauck -

W. Fadden V. Nerses, et al. W. Reed, et al.

ic or erses, Project Manager PWR Project Directorate #5 Division of PWR t.icensing-A cc: See next page Note: The exit meeting is open to interested members of the public to attend as observers. Members of the public who wish to attend this meeting 1986. (must The contact NRC generally V. Nerses does not (301) 492-8535 have no later than access authority May,12, 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 infomation.

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).

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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 Hosue Annex Concord, New Hampshire 03301 Mr. Bruce B. Beckley, Project Manager j Public Service Company of New Hampshire Resident Inspector Post Office Box 330 Seabrook Nuclear Power Station Manchester, New Hampshire 03105 c/o U.S Nuclear, Regulatory Commission Post Office Box 700 Dr. Mauray Tye, President Seabrook, New Hampshire 03874 Sun Valley Association

. 209 Summer Street Mr. John DeVincentis, Director Haverhill, Massachusetts 01839 Engineering and I.icensing Yankee Atomic Electric Company Robert A. Backus, Esq. 1671 Worchester Road O'Neil, Backus and Spielman Framingham, Massachusetts 01701 116 1.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 Hannon, Weiss & Jordan Philadelphia, Pennsylvania 19101 20001 S Street, NW Suite 430 Washington, D.C. 20009 Mr. Philip Ahrens. Esq.

Assistant Attorney General i

State House, Station #6 Augusta Maine 04333 Jo Ann Shotwell, Esq.

Office of the Assistant Attorney General Environmental Protection Division Mr. Warren Hall 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 Connission Mr. Diana P. Randall 631 Park Avenue 70 Collins Street King of Prussia, Pennsylvania 19406 Seabrook, New Hampshire 03874 i Richard Hampe, Esq. I New Hampshire Civil Defense Agency i 1 107 Pleasant Street l l Concord, New Hampshire 03301 i

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Public Service Company 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. l.etty Hett Senator Gordon J. Fumphrey 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 Hampton Falls, New Fampshire Durham Board of Selectmen Drinkwater Road Town of Durham Fampton 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 Comittee Board of Selectmen c/o Rye Town Hall 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 Commission Town Fall 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 Fampshire 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 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 l

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. ENCLOSURE l ELECTRICAL, INSTRUMENTATION AND CONTROL SYSTEMS BRANCH SITE AUDIT AGENDA FOR SEABROOK STATION, UNIT 1 The EICSB staff intends to spend three days at the Seabrook site in an effort to review the instrumentation and controls following the outline provided below. The staff will concentrate its efforts on the items identified with an asterisk (i.e., these items are to be covered during the site visit as a minimum). The remaining items will be audited if time permits. We suggest that the outline be reviewed and, if necessary, be reorganized such that the site visit can be efficiently accomplished within the planned time frame stated above. Also, drawings should be used wherever possible as an aid during the <

site audit review,

1. Preliminary Discussion / Plant Walkthrough 1

a. Plan for touring plant including a general "iscussion d of the plant layout.

b. Preliminary plant walkthrough.

• c. Special Interest Areas:

- [ Intelligent Remote Terminal Units (IRTUs)]

1 Physical inspection of IRTU electronic cabinets and associated termination cabinets for various inputs into IRTUs (i.e., analog, digital,RTDs,andthermocouples);VerificationofA-associated and B-associated signal inputs to IRTUs 1 and 2, B-associated signal inputs to IRTUs 4 and 6, and A-associated power supplies to all IRTUs; Physically inspect and trace 120 Vac distribution I

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cables within electronics cabinets (concentrate on termination points); Verify removal of space heaters.

[FreezeProtection]

Examine freeze protection design features for instrumentation sensing and sampling lines for systems important to safety.

Verify all three methods of freeze protection (Should include plant walkthrough to inspect temperature sensors provided for control room alarms, dual heat tracing on safety-related piping,

. placementofheaters,etc.). (SER7.3.2.12) ,

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2. Control Room

• a. Review general layout of the control room

• b. Examine manual reactor trip controls to verify separation and isolation requirements are met. (SER7.2.1)

• c. Examine overall dispiry instrumentation important to safety.

Concentration will be on:

- The bypassed and inoperable status indication for ESFAS and RPS as it relates to RG 1.47. Particular attention will be on utiliza-tion of the Video Alarm System, utilization of the bypassed and inoperable status panel, and implementation of diesel generator inoperable status indication. (SER7.5.1)

- Post-Accident Monitoring Indication

• d. Inspect instrument cabinets, engineered safeguard cabinets, RPS cabinets,isolationcabinets(arrangements, layout, separation, etc.).

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• e . Review Ro<f position indication.

• f. Review Protection system initiation and status panels.

• g. Review Engineered safety feature initiation and status panels.

• h. Inspect operation of the safety injection accumulator isolation valves. (SER7.6.2)

- Review procedure for removing power from these valves when they are locked in the open position.

- Check visual indication of the open or close status of the valves per requirements of ICSB BTP 18.

- Check for the independent audible and visual alarm provided when the valves are not fully open.

• i. Examine the readouts provided to determine'the position of the pressurizer safety valves and the PORV's. (SER7.5.2.6)

• j. Check for temperature, pressure and level indication for pressurizer relief tank. (SER 7.5.2.6)

• k. Review Panel Cabling / Wiring

- Inspect redundant components and wiring on control panels.

- Verify that physical separation and electrical isolation require-ments are met.

- Verify that protection system wiring and control wiring are i

properly separated.

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• l. Verify emergency feedwater flowrate indication as required by NUREG-0737 Item II.E.1.2, Part 2. (SER7.3.1.7.2)

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*m. Verify additional indicators and alarms to be implemented for instrumentation used for safety functions. (SER7.3.2.4)

• n. Verify low temperature alams (ambient and heat tracing) and loss of power alarms for freeze protection (SER7.3.2.12)

• o. Verify position indication for RHR inlet isolation valves. (SER 7.6.7.5) Should confirm that upon removal of motive power from the

! valve operator, these valves will continue to have operable, redun- 1 dant position indication in control room. (SER7.6.7.3)  !

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• p. Verify control for energization/deenergization of MCCs to prevent spuriousvalveactuation(E522-TrainA,E622-TrainB). Verify alarm for out-of-normal (closed) position. (SER7.6.7.3)

• q. Verify alarm annunciation required to alert operator of the need to initiate manual switchover actions. Include verification of lights on main control board to indicate latched relay via SI signal.

l (SER 7.6.7.6)

• r. Verify alann for RHR suction valves not fully open or flow through RHR pump is below the minimum required for pump protection. ,

(SER7.6.7.7)

• s Verify that emergency procedures written to ensure (If that emergency feedwater flow to steam generator A and C will be normally controlled with the Train A powered flow control valves and (2) that the emergency feedwater flow to steam generators B and D will be, normally controlled from the train B-powered valves. l l

3. Shutdown from Outside the Control Room j 1

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• a. Location of remote shutdown panel.

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• b. General layout of panel.

• c. Identification of controls

• d. Habitability of remote shutdown panel location.

• e. Potential for damage from missiles, flooding, pipe whip, etc.

• f. Verify that physical separation and electrical isolation requirements for redundant instrumentation and controls are met.

• g. Examine the manual transfer switches.

• h. Verify control room annunciation for operation of transfer switches.

• i. Physical walkthrough using emergency procedures required in case of

. control room evacuation (should include discussion on the number of people that would be required to achieve shutdown from outside the control room, the accessability / security of the remote shutdown station (s),etc.).

• j. Verify hot and cold leg temperature indications on the remote shutdown panel.

• k. Concentrate on disabling of SSPS. Discussion should be provided on administrative controls related to this design feature. Relate to RAI 420.38 response which associates deenergization of SSPS with Appendix R.

• l. Concentrat on switchover to the cooling tower from RSP (i.e., go through steps required to initiate from outside the control room).

• m. Verify that all instrumentation loops (transmitters, wiring, and indicators) required for safe plant shutdown from outside the control room will be operable following a seismic event. This should include verification for instrumentation not on RSP that is required for safe shutaown (i.e., CST level, EFW pump suction pressure, etc.).

• n. Verify steps to be taken should a safety injection function occur subsequent to control room evacuation. Relate to RAI 420.76 response and Item k. above. (SER7.3.2.1) l

4. Cable Runs and Cable Spreading Area l

a. General layout.

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• b. Implementation of separation criteria.

(Verify identification of Class IE raceways and check cable identification).

• c. Check routing of power cables (embedded conduit, separate safety-class structure).

• d. Verify that cable penetrations meet physical separation and electrical. isolation requirements.

5. Reactor Building Auxiliary and Turbine Building _

• a. Arrangement of instrument panels / racks associated with plant protection systems (separation and layout).

b. Potential for instrument damage due to missiles, flooding, pipe whip, etc.

c. Component separation and isolation.

• d. Panel wiring separation an'd isolation.

• e. Separation and independence of piping and wiring to redundant

• or diverse instruments.

f. Provisions for testing protection instruments.

6. Reactor Trip System , , .

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a. Motor Generator sets

b. Switchgear 4

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c. Physical and electrical independence

7. ESF Systems and Pump Rooms

a. General arrangements.

• b. Switchgear rooms.

c. Physical and electrical independence.

d. Potential for damage due to flooding, missiles, etc.

• e. Provisions for testing (shuuld include walkthrough of typical actuation channel test per technical specifications from sensors to and including actuation of final actuated devices).

f. Cabling and equipment identification.

• g. Examine test features required to facilitate testing of P-4 interlocks. (SER7.3.2.3) ,

8. Instrument Piping

a. Physical separation.

b. Potential for damage from missiles, flooding, pipe whip, etc.

. 9. Circuit Traces from Sensors to Final Actuation Devices

a. Check the wiring and circuitry associated with the turbine trip input i to the reactor protection system. Trace wiring for redundant chan- l nels of the trip systems from the trip devices (sensors) through to the RPS cabinets. Verify isolation devices. (SER7.2.2.5)

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• b. Trace the instrument piping and circuits for redundant channels of the pressurizer inputs to the protection system (from instrument piping to transmitter to RPS and ESFAS cabinets to final actuated devices).

• c. Trace the turbine trip upon reactor trip circuitry. Verify that the maximum credible faults were considered in routing of these circuits within the turbine building. Check isolation devices used to prevent degradation of RPS due to credible faults within the turbine build-ing. (SER 7.2.2.4)

• d. Trace circuitry associated with Radiation Data Management System (RDMS).

- Trace redundant circuits from Class IE radiation detector to Class IE RM 80 assembly through to actuated equipment.

Physically inspect Class IE RM 80 assemblies - Include (1) verification of separation between redundant Class IE RM 80 assemblies, (2) inspection of motherboard and associated connec-tions, (3) inspection of power / isolation board and connections, (4) inspection of customer interface junction boxes with concen-tration on special fuse assemblies and fuse board mounting for special fuses, transorb devices, etc.

- Trace typical circuit from RM 80 to RM 23 (Verify that RM 23 is Class IE and does not interface with non-safety related equipment; verify Train A and Train B separation) '

Trace redundant circuits to CP-180 cabinets in the control room:

Include (1) verification that CP-180 cabinets are Class 1E, (2)physicalinspectionofCP-180 cabinets,(3)discussionon purpose for and design features of the CP-180 cabinets, and i 1

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(4) verification of Train A and Train B separation (Refer to Figure 1 of FMEA for RDMS).

11. Vital Instrumentation and Control Power Supply Installation

a. General layout.

b. Physical and Electrical separation.

c. Potential for damage from missiles, high energy line break, etc."

d. Batteries, inverters, etc.

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