ML18092A876
| ML18092A876 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/17/1985 |
| From: | Corbin McNeil, Corbin McNeil Public Service Enterprise Group |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18092A877 | List: |
| References | |
| GL-83-28, LCR-84-13, NUDOCS 8510250081 | |
| Download: ML18092A876 (8) | |
Text
Public Service Electric and Gas Company Corbin A. McNeill, Jr.
Vice President -
Public Service Electric and Gas Company P.O. Box236, Han cocks Bridge, NJ 08038 609 339-4800 Nuclear U.S. Nuclear Regulatory Commission Off ice of Nuclear Reactor Regulation Division of Licensing Washington, D. C. 20555 Attention:
Mr.
Steven A.
Varga, Chief Operating Reactors Branch 1 Division of Licensing Gentlemen:
REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE DPR-70 UNIT NOS.
1 AND 2 SALEM GENERATING STATION DOCKET NOS.
50-272 AND 50-311 October 17, 1985 Ref:
LCR 84-13 In accordance with the Atomic Energy Act of 1954, as amended and the regulations thereunder, we hereby transmit copies Qf our request for amendment and our analyses of the changes to Facility Operating Licenses DPR-70 and DPR-75 for Salem Generating Station, Unit Nos. 1 and 2.
This* amendment request consists of adding specifications responsive to Generic Letter 83-28 regarding Reactor Trip Breaker Automatic Shunt Trip.
In accordance with* the fee requirements of 10CFR170.21, a check in the amount of $150.00 is enclosed.
(--a51025ooe1 s5tot7 I *. PDR ADOCK 0500~s~2.
p
Mr.
Steven A.
Varga October 17, 1985 Pursuant to the requirements of lOCRFS0.91, a copy of this request for amendment has been sent to the State of New Jersey as indicated below.
This submittal includes three (3) signed originals and forty (40) copies.
Enclosure C
Mr. Donald c. Fischer Licensing Project Manager Mr. Thomas J. Kenny Senior Resident Inspector Mr. Samuel J. Collins, Chief Projects Branch No. 2, DPRP Region 1 Sincerely, Mr. Frank Cosolito, Acting Chief Bureau of Radiation Protection Department of Environmental Protection 380 Scotch Road Trenton, N.J. 08628 Honorable Charles M. Oberly, III Attorney General of the State of Delaware Department of Justice 820 North French Street Wilmington, Delaware 19801
.e Ref:
LCR 84-13 STATE OF NEW JERSEY SS.
COUNTY OF SALEM Corbin A. McNeil!, Jr., being duly sworn according to law deposes and says:
I am a Vice President of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated October 17, 1985, concerning our Request for Amendment to Facility Operating Licenses* DPR-70 and DPR-7 5, are true to the. best of my knowledge, information and belief.
Subscribed and Sworn to before me this /7'1:.AJ day of ~~
, 1985 Notary Public of New Jersey DONNA G. HITCHNER NOTARY PUBLIC OF NEW JERSEY My commission expires on _____
M_y_c_om_m_i_ss_io_n_E_x_pi_re_s_M_a_rc_h_24_,_1_98_7 _____ _
.e PROPOSED CHANGE TO ENVIRONMENTAL _TECHNICAL SPECIFICATIONS SALEM GENERATING STATION UNIT NOS. 1 AND 2 Description of Change Ref:
LCR 84-13 Change Technical Spe9ifications Section 4, Table 4.3-1 for Salem Unit Nos. 1 and 2 to agree with the attached revised pages.
Reason for Change This change will add specifications that are responsive to NRC staff requirements identified in Items 10 and 13 of their SER for the PSE&G response to Item 4.3 of Generic Letter 83-28, "Reactor Trip Breaker Automatic Shunt Trip'~ dated June 25, 1984.
10CFRS0.92 EVALUATION FOR NO SIGNIFICANT HAZARDS CONSIDERATION This change adds surveillance requirements for the Reactor Trip Circuitry not presently included in the Technical Specifications.
This corresponds to Example(ii) of the guidance
- provide.Q by the Commission in 48FR14870* for Examples Of Amendments That Are Considered Not Likely To Involve Significant Hazards Considerations. *A description of the shunt trip modifications is included as an attachment.* Since the addition of the automatic shunt trip increases the margin of *safety, in no.
way creates the possibility _for a new accident not previously
- considered in the safety analyses, and does not increase the possibility or consequences of any previously analyzed accident, we have determined that this change to the Technical Specifications does not involve a signific~nt hazards consideration.
Ref/LCR's
OPS~G
- Page 1 of 3 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038
~-*.
Nuclear Department EVALUATION FOR AUTOMATIC SHUNT TRIP
1.0 SCOPE
This document*applies to the modification of the Reactor Protection System (RPS) such that the reactor trip breakers will be opened by the shunt trip coil mechanisms in conjunction with the undervoltage trip*mechani~m-for th~
automatically initiated reactor trip signal from the solid state protection system (SSPS).
2.0 REFERENCES
2.1 Westinghouse Solid State Protection System Manual 2.2 NRC General Design Criteria 2.3 CDS-1 Rev. 5 Design Criteria For Independence And Separation Of Safety Related Instrumentation Controls And Protection System.
3.0 BACKGROUND
The reactor trip breakers are used.to interrupt power from the* rod control motor.generator sets to the reactor control rod drive mecha"nisms.
When either of the redundant reactor
- trip breakers are opened, the control rods drop into the reactor core.
There are two reactor trip breakers and two bypass breakers installed in a configuration as shown on sketch tl.
In normal operation, the reactor trip breakers "A" and "B" are in service and bypass breakers "A" and "B" are racked out of service.
The bypass breakers "A" and "B" are used to permit surveillance testing of reactor trip breakers 11 An and "B" during power operations.
Each of the four reactor trip breakers incorporate an undervoltage trip and shunt trip m~cnanism *. The breakers may be tripped open by deenergizing the undervoltage coils or by energizing the shunt trip coils.
The breakers may be opened manually by either of two reactor trip switches mounted on the control console.
The manual trip switches interrupt the power supplied to the undervoltage coils from the SSPS in conjunction with energizing the shunt trip mechanism of the breakers.
95.z. 63 08CM1 ' I -~z
Pa 2 Of 3 The SSPS utilizefl the undeli'voltage mechanisms to*
automatic.ally open.the breakers by removing power from the normally enerqized undervoltage coils.
4.0 DISCUSSION
The shunt.trip mechanism may be used to insure the opening of the reactor trip breakers via the automatic trip signal from the SSPS without degrading the performance of the RPS or the perfo~ance of any other protection function.
A relay paralleled to the u.v. coils on the output of the SSPS u.v. driver printed circuit card may be used to energize the shunt trip coil of the re'actor trip breakers.
The u.v. driver card is capable of 4 amperes output and the two u.v. devices presently installed on the breakers utilize only 400*milliamperes of that output.
The added relay ~ill apply an additional load to the u.v. driver card of approximately 226 milliamperes which is well within the capability of the u.v. driver*card.
To enhance the modification utilizing the shunt trip mechanism, the change is in accordance with all requirements normally associated with protection systems with the exce~tion of the failure mode criteria in General Design Criteria 2_3 since electrical power is required to initiate a reactor trip via the shunt trip mechanism.
The 12S volt o.c. power supply used to energize the shunt trip device is from a highly reliable class IE vital power supply.
The nA" react6r trip breaker is fed from the "A" 125 volt o.c. battery system while*the "B" reactor trip breaker is fed from the "B" 125 volt battery system.
The design also provides a control room-console audible and light indication alarm in the event that either 125 volt supplies are lost or c~ntinuity through either shunt trip coil is lost.
Test switches have been placed in the circuitry to provide on* line operability testing of the circuitry wiring, and independent operation of the shunt trip mechanism and the u.v. mechanism.
The placement of the test switches and procedural testing steps which will be used will_ also verify that the spring return switches have returned to thei_r. required normal position.*
Pa 3 of 3.
The required additional field cabling and all additional co111Ponent.s have been. designed per the requirements of CDS-1 Rev. 5 *oesign Criteria for Independence and Separation of safety Related Instrumentation, Controls and Protection Systems.
The equipnent being added to implement this change has been seismically qualified except for the shunt trip mechanism and shunt trip relay.
Westinghouse, the breaker manufacturer and* supplier of *the relay, has committed to the Nuclear Regulatory Commission to seismically qualify these two components.
The relay being installed is the relay recommended in the w.o.G. generic design which has been approved by the Nuclear Regulatory Commission.
Also ~he equipuent that is being installed has been designed to operate during the most severe environmental conditions that may occur in the location in which they will be installed.
5.0 CONCLUSION
S:
The installation of equipment to operate the shunt trip mechanisms on the reactor trip breakers will enhance the operability of the reactor trip b~eakers and insure their automatic opening when required by the RPS.
The installation will not result in an unreviewed safety question.
CONT~.L ROO
.ORl./e MECHANISM
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