ML20135C252
| ML20135C252 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 09/09/1985 |
| From: | Devincentis J PUBLIC SERVICE CO. OF NEW HAMPSHIRE |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, SBN-868, NUDOCS 8509110369 | |
| Download: ML20135C252 (20) | |
Text
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SEABROOK STATION EnE neering Office i
PutAC Setylce of New @
Now Hampshire Yonkee Divlelen September 9, 1985 SHN-868 T.F. H4.2.99 United States Nucicar Regulatory Commission Washington, D. C. 20555 Attention:
Mr. George W. Knighton, Chief Licensing Branch No. 3 l
Division of Licensing
References:
a.
Construction Permits CPPR-135 and CPPR-136, Docket Nos. 50-443 and 50-444 b.
USNRC Letter, dated July 8, 1983, " Required Action unsed on Generic Implication of Salem ATWS Evento (Generic Letter 83-28)" D. G. Eisenhut to all Licensees of Operating Reactors, Appilcants for Operating License and Holders of Construction Permits c.
USNRC Letter, dated August 10, 1983, " Safety Evaluation Report on the Generic Westinghouse Design for Automatic Shunt Trip Actuation," D. G. Eisenhut to J. J. Sheppard (WOG) d.
PSNH Letter (SBN-516), dated November 4, 1983, " Response to Conoric Letter 83-28," J. DeVincentin to G. W. Knighton
Subject:
Additional Response to Generic Letter 83-28 (Positions 4.1 and 4.3)
Dear Sir:
Provided herewith are Encionures 1 and 2 which contain the plant-specific information requested in Position 4.3 of Reference (c).
The enclosed, however, is a partial response since plant-specific test procedures have not been completed at this time (i.e., cannot " verify" procedure content).
l However, these responses do provide the bania on which we intend to proceed l
with developing the procedures.
A completed response for these items will be made by November 29, 1985.
Although not applicable to the request for plant-opecific information, it should be noted that the equipment modifications discussed in responso to Generic Letter 83-28, Positions 4.1 and 4.3 (Reference (d)), have been completed for Unit 1.
The modification described in Position 4.1 was also identified to Region I as a 10CFRSO.55(o) deficiency (Reference CDR 83-00-07).
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. a oux JUO. Wook,NH 03874 Tolophone(603)474 9521 It e i
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United States Nuclear Reguistory Coeumleston AttentLon Mr. George W. Knighton Page 2 i
i We request that you review the enclosed and advloe by October 18, 1985 that the completed responses are acceptable.
f Very trul yours, ge/
John DeVincentis Director Engineering and Licensing Enclosures cci Atomic Safety and Licensing Board service List l
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William S. Jordan, 111 Donald E. Chick l
Diane Curran Town Manager Harmon, Weiss & Jordan Town of Lxeter 1
20001 S. Street, N.W.
10 Front Street Suite 430 Exeter, NH 03833 Washing ton, D.C.
20009 Brentwood Board of Selectmen l
Robert C. Perlie RED Dalton Road Office of the Executive Legal Director Brentwood, Nil 03833 U.S. Nuclear Regulatory Commission Washington, DC 20555 Richard E. Sullivan, Mayor City llall Robert A. Backus, Esquire Newburyport, MA 01950 116 Lowell Street P.O. Box 516 Calvin A. Canney Manc he s te r, NH 03105 City Manager City llall Philip Ahrens Esquire 126 Daniel Street Assistant Attorney Ceneral Portsmouth, Nil 03801 Augusta, NE 04333 Dana niebec. Esquire Mr. John B. Tanaer Assistant Attorney Cen*ral Designated Representative of Of fice of the Attorney General the Town of Hampton 208 State liouse Annex 5 Norningside Drive Concord, NH 03301 l
Ilampton, Nil 03842 Anne Verge, Chairperson Roberta C. Pevear Board of Selectmen Designated Representative of Town llall l
the Town of flampton Falls South flampton, Nil 03827 l
Drinkwater Road l
llampton Falls, Nil 03844 Patrick J. McKeon l
Selectmen's Office Mrs. Sandra Cavutis 10 Central Road Designated Representative of Rye, Nil 03870 the Town of Kensington RFD 1 Carole F. Kagan, Esquire East Kingston, Nil 03827 Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Comminston Jo Ann Shotwell, Esquire Washington, DC 20555 Assistant Attorney General Environmental Protection Bureau Hr. Angi 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 l
Senator Cordon J. Ilunp'orey Town Manager's Office U.S. Senate Towr. I!all - Friend Street Washington, DC 20510 Amesbury, MA 01913 (ATTN Tom Burack)
Senator Cordon J. Humphrey Diana P. Randall 1 Pillsbury Street 70 Collins Street Concord, Nil 03301 Seabrook, Nil 03874 (ATTH: lierb Boynton)
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i SBII-868 l
I EBCLOSURE 1 Plant-Specific (*r: brook) Desten Information Roeuired for Westinnhouse Plants Incorporatina the Autcastic Shunt Trio llodificat%on l
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SBN-868 ENCLOSURE 1 plant-Specific (Seabrook) Desian Information Required for Westinahouse Plants Incorporating the Automatic Shunt Trio Modification i
1.
Request
" Provide the electrical schematic / elementary diagrams for the reactor trip and bypass breakers showing the undervoltage and shunt coil actuation circuits as well as the breaker control (e.g., closing) circuits and circuits providing breaker status information/ alarms to the Control Room."
Response
Electrical schematic diagrar.s for the reactor trip and bypass breakers are provided in Enclosure 2.
2.
Request
" Identify the power sources for the shunt trip coils. Verify that-they are Class lE and that all components providing power to the shunt trip circuitry are Class lE and that any faults within non-class lE circuitry will not degrade the shunt trip function.
Describe the annunciation / indication provided in the Control Room upon loss of power to the shunt trip circuits. Also describe the overvoltage protection and/or alarms provided to prevent or alert the operator (s) to an overvoltage condition that could affect both the UV coil and the parallel shunt trip actuation relay."
Response
Control power for the reactor trip and bypass breaker shunt trip coils is supplied from the Class lE 125 V de station batteries and de distribution system. There is no non-Class lE circuitry whose failure'could degrade
~the Class lE shunt trip circuitry.
Indication of power availability to the shunt trip coil circuits is provided by the circuit breaker red (closed) and green (open) position indication lights. Normally, one light would be on depending on breaker position.
If both lights are out, this would indicate a problem with power availability.
In addition, various auxiliary relays are picked up when the reactor trip breakers are closed for normal power. operation.
Loss of control power would cause the relays to drop out. The resulting incorrect indication and alarm would lead to detection of the loss of control power.. Loss of control power caused by loss of the de system (loss of power to the 125 V de distribution panel) would be alarmed.by-the de system undervoltage alarms.
The UV coil and the parallel shunt trip actuation relay receive power from the Solid State Protection System (SSPS). The power supply within
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the SSPS has overvoltage protection set at 115% of nominal voltage -
W 4
4 ENCLOSURE 1 (Continued)
(48 V dc). The UV coil and the parallel shunt trip actuation relay have been designed to perform their function up to a voltage as high as 115%
of nominal voltage.
3.
Request
" Verify that the relays added for the automatic shunt trip function are within the capacity of their associated power supplies and that the relay contacts are adequately sized to accomplish the shunt trip function.
If the added relays are other than the Potter & Brumfield MDR series relays 4
i (P/M 2383A38 or P/M 955655) recommended by Westinghouse, provide a description of tl.a relays and their design specifications."
Response
i The automatic shunt trip modification has been purchased as a package from Westinghouse. Westinghouse has verified that the relays are within the capacity of their associated power supply and that the relay contacts 4
are adequately sized to accomplish the shunt trip function. The relays provided for the Seabrook modification are Potter & Brumfield MDR series relays, Westinghouse Part Number 955655.
4.
Request
" State whether the test procedure / sequence used to independently verify operability of the undervoltage and shunt trip devices in response to an 4-automatic reactor trip signal is identical to the test procedure proposed by the Westinghouse owners Group (WOG).
Identify any differences between the WOG test procedure and the test procedure to be used and provide the rationale / justification for these diffarences."
f
Response
i Seabrook's test procedure will be identical to the procedure proposed by the Westinghouse Owners Group (WOG) which was contained in WOG Letter Number OG-101 from J. J. Sheppard to D. G. Eisenhut, dated i
June 14, 1983. Upon completion of plant-specific procedures, we will confirm the procedures are identical.
5.
Request
" Verify that the circuitry used:to implement the automatic-shunt trip function is Class'1E (safety-related), and that the procurement, 4
installation, operation, testing and maintenance of this circuitry will 4
be in accordance with the quality assurance criteria set forth in Appendix B to 10 CFR Part 50."-
Response
The circuitry used to implement the automatic shunt trip function is class 1E (safety-related) and therefore, the procurement, installation, operation, testing and maintenance of this circuitry will be in,
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4 ENCLOSURE 1 (Continued) accordance with the quality assurance criteria set forth in Appendix B to 10 CFR Part 50, 6.
Request
" Verify that the shunt trip attachments and associated circuitry are/will be seismically qualified (i.e., be demonstrated to be operable during and after a seismic event) in accordance with the provisions of Regulatory Guide 1.100, Revision 1, which endorses IEEE Standard 344 and that all nonsafety-related circuitry / components in physical proximity to or associated with the automatic shunt trip function will not degrade this function during or after a seismic event."
Response
The shunt trip attachment and associated circuitry have been seismically qualified by Westinghouse in accordance with the provisions of Regulatory Guide 1.100, Revision 1, which endorses IEEE Standard 344.
Since the automatic shunt trip circuitry / components are mounted in the reactor trip switchgear which has been selsrically qualified, there are no nonsafety-related circuitry / components which can fait and degrade the automatic shunt trip functions during or after a seismic event.
7.
Request
" Verify that the components used to accomplish the automatic shunt trip function are designed for the environment where they are located."
Response
The components used to accomplish the automatic shunt trip function have been designed and tested for the environment of the Switchgear Room as follows:
Normal Temperature 0
Seabrook Environment 55-104 F Westinghouse Qualification 60-1040F 1
The slightly lower minimum temperature of the Switchgear Room will not effect the operation of the Reactor Trip Switchgear.
Abnormal Temperature 0
Seabrook Environment 107 F maximum for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Westinghouse Qualification 1200F maximum for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> The qualification temperature. envelopes the actual temperature.,p-sq y-ye y
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l ENCLOSURE 1 (Continued)
Humidity Seabrook Environment 60% maximum Westinghouse Qualification 95% maximum i
The qualification humidity envelopes the actual humidity.
pressure Seabrook Environment Slightly positive Westinghouse Qualification Atmospheric 4
j The slightly positive pressure will not effect the operation of the
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Reactor Trip Switchgear.
1 Radiation
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Seabrook Environment
< 1 x 103 R Westinghouse Qualification
< 1 x 104 R The qualification radiation envelopes the actual radiation levels.
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Margin was added to the above qualification parameters during the-j qualification program.
1 8.
Request
" Describe the physical separation provided between the circuits used to j
manually initiate the shunt trip attachments of the redundant reactor
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trip breakers. If physical separation is not maintained between these circuits, demonstrate that faults within these circuits cannot degrade both redundant trains."
Response
The control switches (reactor trip and safety injection). to manually initiate the shunt trip attachment to provide reactor trip are' located on the main control board. The redundant train wiring is separated on the
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control switches by barriers and is routed in separate conduits / wireways I
within the main control board to terminal blocks for termination of field cable. The redundant train cabling from the main control board to_the 1
reactor trip switchgear is routed in separate raceways. Within the reactor trip switchgear, the wiring is routed in separate wireways in i
accordance with the standard Westinghouse design. The automatic shunt J
4 trip panels are located within the switchgear enclosure for their j
respective train. ' The above-separation is in accordance with the physical separation criteria as given in the FSAR.
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ENCLOSURE 1 (Continued) 9.
Request
" Verify that the operability of the control Room manual reactor. trip switch contacts and wiring will be adequately tested prior to startup after each refueling outage. Verify that the test procedure used will not involve installing jumpers, lif ting. leads, or pulling fuses and identify and deviations from the WOG procedure. Permanently installed test connections (i.e., to allow connection of a voltmeter) are acceptable."
Response
The operability of the Control Room manual reactor trip switch contacts and wiring will be tested prior to startup after each refueling outage.
Westinghouse has indicated that the only procedure they have for testing the manual trip switches was contained in Westinghouse Technical i
Bulletin 83-03; however, that procedure required installing jumpers and removing fuses. Seabrook's procedure will follow the general concept of the Technical Bulletin, but will use portable voltmeters to monitor operation of the manual trip switch contacts and will not involve installing jumpers, lif ting leads or removing fuses. Upon completion of plant-specific procedures, we will confirm procedure compliance with the above.
10.
Request
" Verify that each bypass breaker will be tested to demonstrate its operability prior to placing it into service for reactor trip breaker testing."
t
Response
Plant procedures will require that each bypass breaker will be tested, using the local -lose and trip pushbutton switches, to demonstrate its operability prior to placing it into service for reactor trip breaker testing. Upon completion of plant-specific procedures, we will confirm procedure compliance with this requirement.
11.
Request
" Verify that the test procedure used to determine reactor trip breaker operability will also demonstrate proper oporation of the associated Control Room indication / annunciation."
Response
Plant procedures will verify proper operation of the Control Room indication / annunciation during operability testing of the reactor trip breakers. Upon completion of plant-specific procedures, we will confirm procedure compliance with this requirement.:
1 ENCLOSURE 1
)
(Continued) 12.
Request
" Verify that the response time of the automatic shunt trip feature will be tested periodically and shown to be less than or equal to that assumed in the FSAR analyses or that specified in the Technical Specifications."
Response
The response time of the automatic shunt trip feature will be periodically tested. Upon completion of plant-specific procedures, we will confirm procedure compliance with this requirement.
13.
Request
" Propose Technical Specification changes to require periodic testing of the undervoltage and shunt trip functions and the manual reactor switch contacts and wiring."
Response
Technical Specifications for the reactor trip breakers and the manual reactor switch contacts and wiring will be addressed during the review and finalization of Seabrook's Technical Specifications.
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SBN-868 ENCLOSURE 2 Schematic Diagrams
SBN-868 Schematic Number 9763-M-310944 Sheets: HD2a HD2b HD2e HD3a HD3b HD3e HD3d HD3e LEGEND RTA - Reactor Trip Breaker, A Train BYA - Bypass Breaker, A Train RTB - Reactor Trip Breaker, B Train BYB - Bypass Breaker, B Train F42 - Typical node number, "F" indicates located in Main Control Room HD3 - Typical node number, "H" indicates located at Reactor Trip Switchgear M-310949 - Schematic number, indicates interface with Solid State Protection System M-310181 - Schematic number, indicates interface with Station Computer System for alarms i
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