ML18106A347
| ML18106A347 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/03/1998 |
| From: | Milano P NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9803050049 | |
| Download: ML18106A347 (16) | |
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5'0-272 LICENSEE:
FACILITY:.
SUBJECT:
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 3, 1998 Public Service Electric and Gas Company Salem Nuclear Generating Station, Unit No. 1
SUMMARY
OF JANUARY 8, 1998, MEETING REGARDING CABLE SEPARATION REQUIREMENTS This summary refers to the meeting with Public Service Electric and Gas Company (PSE&G) condueted on January 8, 1998, at the U.S. Nuclear Regulatory Commission (NRC) office in Rockville, Maryland. The meeting was held at the request of PSE&G to discuss the design basis and the application of the Institute of Electrical and Electronics Engineers (IEEE) Standard 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Stations," to the interface relay cabinets at the Salem Nuclear Generating Station, Unit No. 1. Specifically, the meeting addressed concerns that were being raised by an ongoing plant inspection. A list of the attendees at the meeting and a copy of the slides presented by PSE&G are enclosed (Enclosures 1 and 2, respectively).
The PSE&G presentation followed closely the material in their slides and back.up simplified cable diagrams (Enclosure 3) provided at the meeting. The PSE&G presentation provided (a) an overview of the Salem cable separation design and licensing basis, (b) a description of how the design criteria was implemented in PSE&G Control Division Functional Specification CD-S-1, "Design Criteria for Independence and Separation of Safety Related Instrumentation, Control and Protection Systems," and (c) a brief review of the cable separation and design implementation of the electrical system for the control room interface panels.
P~E&G noted that the concerns that were raised regarded the design of the control room interface panels. These panels are completely separate from those associated with automatic protective functions and engineered safety features (ESF) actuation, and no protective channels are routed through these panels. The interface panels provide a low voltage ac and de interface for manual controls and indication in the control room. These low voltage systems are also non-ground such that two faults are needed to create a ground. PSE&G finally noted that no credible failure in this interface bus would preclude a reactor trip or ESF actuation.
PSE&G discussed the specific design of several of the areas where the NRC inspector had noted the location of multiple channels with the same panel. PSE&G described how, based on the engineering philosophy used during the design and construction period for Salem, a fault affecting these cables would not be propagated. On the basis of these discussions, PSE&G committed to document the identified cable separation problems in condition reports (CRs) and
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to analyze by engineering evaluation that any problems will not be propagated such that a loss
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- of function may occur. Further, PSE&G committed to provide reasonable assurance that the situations analyzed are indeed typical and bounding for all situations. The results of these commitments would be provided to the NRC inspector for his review. The resolution of this issue will be required prior to the plant entering Mode 2 (startup).
Docket No. 50-272
Enclosures:
- 1. Attendance List
- 2. PSE&G Slides
- 3. PSE&G Handouts cc w/enclosures:
See next page DISTRIBUTION:
Docket File PUBLIC E-MAIL:
SCollins/FMiraglia BBoger JZwolinski JStolz JCalvo Isl Patrick D. Milano, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation PDl-2 Reading File OGC GSBarber, RI DThatcher JKnox PMilano TClark JRoe (e-mail to SLM3)
ACRS BMcCabe, OEDO JLinville, RGN-1 WRuland, RGN-1 ADellaGrecca, RGN-1 MEvans, Salem SRI OFFICE PDl-2/~-
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PDl-2/LA DET/EELB/C PDl-2/D NAME viv PMilano:
TClar~ t/\\G DATE 01 ti3t98 01~98 OFFICIAL RECORD COPY DOCUMENT NAME: SA1-8.MTS JCalvo (1,4l ~
011Z6198 01/ i 7198 f
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of function may occur. Further, PSE&G committed to provide reasonable assurance that the situations analyzed are indeed typical and bounding for all situations. The results of these commitments would be provided to the NRC inspector for his review. The resolution of this issue will be required prior to the plant entering Mode 2 (startup).
Docket No. 50-272
Enclosures:
- 1. Attendance List
- 2. PSE&G Slides
- 3. PSE&G Handouts cc w/enclosures:
See next page Patrick D. Milano, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Mr: Harold W. Keiser Public Service Electric & Gas Company cc:
Mr. Jeffrie J. Keenan, Esquire Nuclear Business Unit - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 General Manager - Salem Operations Salem Nuclear Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Louis Storz Sr. Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Senior Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Maryland Office of People's Counsel 6 St. Paul Street, 21st Floor Suite 2102 Baltimore, MD 21202 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company 965 Chesterbrook Blvd., 63C-5 Wayne, PA 19087 Mr. Elbert Simpson Senior Vice President-Nuclear Engineering Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038
. Salem Nuclear Generating Station, Units 1 and 2 Richard Hartung Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Manager-Licensing and Regulation Nuclear Busienss Unit - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Manager - Joint Generation Atlantic Energy 6801 Black Horse Pike Egg Harbor Twp., NJ 08234-4130 Carl D. Schaefer External Operations - Nuclear Delmarva Power & Light Company P.O. Box 231 Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division Chief Engineer 6 St. Paul Centre Baltimore, MD 21202-6806
MEETING ATTENDANCE LIST Licensee: Public Service Electric and Gas Company Plant(s): Salem. Unit 1
Subject:
Electrical Cable Separation Date:
January 8. 1998 Location: NRC Offices. OWFN Room 4-B-6 NAME NRC STAFF J. F. Stolz J. A. Calvo P. D. Milano D. F.. Thatcher J. L. Knox J. C. Linville W. H. Ruland A. L. Della Grecca M. G. Evans G. S. Barber B. McCabe PSE&G.
E. C. Simpsonn D. R. Powell D. F. Garchow G. Boerschig V. Fregonese J. M. O'Connor State of NJ D. Zannoni R. Pinney PUBLIC D. Lochbaum B. Williamson P. Gunter Project Director Branch Chief Sr. Project Manager Section Chief Sr. Electrical Engineer Branch Chief Branch Chief Sr. Reactor Engineer Sr. Resident Inspector Project Engjneer Regional Coordinator Sr. Vice President Director Director Manager Manager Supervisor Nuclear Engineer Nuclear Safety Engineer Associate Editor Time:
10:00 a.m.
ORGANIZATION NRR/DRPE/PD1-2 NRR/DET/EELB NRR/DRPE/PD1-2 NRR/EELB NRR/EELB RGN-1 RGN-1 RGN-1 RGN-1/Salem RGN-1 OEDO Nuclear Engineering Lic/Regul & Fuels Design Engineering Electrical/l&C Design Basis & Conf Electrical Bureau of Nuclear Engineering Un. of Concerned Sc.
Nucleonics Week NIRS Enclosure (1)
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- 1. CABLE 2SSS-BT WHICH Ccr.TAINS SIGNALS THAT CONTR(l BLOWDOWN SAaf>LE VAL YES
- 2. CABLE 2GBT-CT WHICH Ccr.TAINS SIGNAL GENERAT~
BLOWDOWN IS(l.ATION VALVES
- 3. CABLE 2F1228-HO WHICH Ccr.TAINS INSTRUl(NT SIGNALS F~ FEEDIATER HEATER CONTROL ENCLOSURE (3)
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- 1. CABLIE 2RP382-ET MAIN STEAM ISOCATION VALVE POSITION INDICATllJ4
- 2. CABL[ 2VNT73-CT SIGNALS ASSOCIATED WITH CONTRCl ROOM A/C DAJ.FERS
- 3. CABL[ 2ANN448-FT ANNUNICATOR INPUTS
- 4. CABLE 2FW228-HO INSTRUa.ENT SIGNALS FOR FEEDWATER HEATER CONTROL P1\\miscdwgs\\John O'Connor.dgn
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Separation of Wiring ILLI Internal to Panels r"
at A! I Sa/em Nuclear Generating Station I
ENCLOSURE (2)
end a
. Design Basis Hftrn~:r11 11 Reasonable Assurance I *Closure
sign Basis EE-279-1971 Section 4.6 states:
"4.6 Channel Independence. Channels t11at provide signals for the same protective function shall be independent and physically separated to accomplish decoupling of the effects of unsafe environmental factors, electric transients, and physical accident consequences documented in the~ design basis, and to reduce the likelihood of interaction between channels during maintenance, operations, or in the event of channel malfunction."
ensing Basis Preliminary Facility Description and Safety Analysis Report (PFDSAR)
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!plementing Design Criteria PSE&G Controls Division Functional Specification CD-S-1, "Design Criteria for Independence and Separation of Safety Related Instrumentation, Controls and Protection Systems" Sole purpose is to ensure design meets the requirements of IEEE Standard 279-1971, paragraphs 4.1, 4.2, 4.5, 4.6, and 4.22.
iplementing Design Criteria CD-S-1 provides guidelines for separation of wiring to and within field instrument panels according to the following:
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- To the extent possible, wiring of only one safety channel is located in any given panel.
- If wiring of redundant safety functions is to be located in the same panel, it needs to be either physically separated per provided guidance or separated by use of a suitable barrier.
- Wiring arrangement must ensure no loss of redundant safety function.
asonable Assurance Design standards consistent with 0f9Sign and Licensing Basis Ill l~J::!!!llli:!!:!!lll!!ll Review*ot Corrective Action Progra,m does not I
demonstrate problem with wiring separation internal i
to panels
- Design of electrical system for panels and consoles
- Additional Reviews
nclusions Salem's Design and Licensing Bashs regarding wiring
.,.,,.,*& separation internal to panels meets the requirements II of IEEE 279-1971.
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- Engineering reviews and follow up to questions 1~11;;:~:::i:1lll during NRG staff review have revealed no safety I
issues.
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- PSE&G considers this issue closed..
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