ML20008F578
| ML20008F578 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/17/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| References | |
| TASK-06-04, TASK-6-4, TASK-RR LSO5-81-04-017, LSO5-81-4-17, NUDOCS 8104210307 | |
| Download: ML20008F578 (5) | |
Text
UNITED STATES E *i -
~' k NUCLEAR 14EGULATORY COMMISSION WASHINGTON,D.C 20655 g-
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f April 17, 1981 Docket No. 50-219 LS05-81 04-017
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Mr. I. R. Finfrock, Jr.
/f Vice President
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3 Jersey Central Power & Light Company Oyster Creek Nuclear Generating Station f.g 0,9 '
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C Post Office Box 388
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Forked River, New Jersey 08731 Q.
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Dear Mr. Finfrock:
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SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION FOR SEP TOPIC 'fI-4, CONTAINMENT ISOLATION SYSTEMS (0YSTER CREEK)
During our review of SEP Topic VI-4, " Containment Isolation Systens" we found that additional information (see enclosed) is needed to complete our re/iew. Provide your response within 30 days of the receipt of this letter so that our evaluation can be completed in a timely mar.c9r.
Sincerely, N1 h l
Dennis M. Crutchfie d, Chi Operating Reactors Branch No. 5 Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
See next page l
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ssa ass Me) 810.4 210 N
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Mr. I. R. Fi nf rock, J r.
cc G. F. Trowbridge, Esquire Gene Fisher Shaw, Pittman, Potts and Trowbridge Bureau Chief 1800 M Street, N. W.
Bureau of Radiation Protection Washington, D. C.
20036 380 Scotts Road Trenton, New Jersey 08628 GPU Service Corporation ATTN: Mr. E. G. Wallace Commissioner Licensing Manager New Jersey Department of Energy 260 Cherry Hill Road 101 Commerce Street Parsippany, New Jersey 07054 Newark, New Jersey 07102 Natural Resources Defense Council Plant Superintendent 91715th Street, N. W.
Oyster Creek Nuclear Generating Washington, D. C.
20006 Station P. O. Box 388 Forked River, New Jersey 08731 Steven P. Russo, Esquire 248 Washington Street Resident Inspector P. O. Box 1060 c/o U. S. NRC Toxs River, New Jersey 08753 P. O. Box 445 Forked River, New Jersey 08731 Joseph W. Ferraro, Jr., Esquire Deputy Attorney General Director, Criteria and Standards State of New Jersey Division Department of Law and Public Safety Office of Radiation Prograns 1100 Raynond Boulevard (ANR-460)
Newark, New Jersey 07012 U. S. Environmental Protection Agency Ocean County Library Washington, D. C.
20460 Brick Township Branch 401 Chambers Bridge Road U. S. Environmental Protection l
Brick Town, New Jersey 08723 Agency Region II Office Mayor ATTN: EIS C0ORDINATOR Lacey Township 26 Federal Plaza P. O. Box 475 New York, New York 10007 Forked River, New Jersey 08731 Cornissioner Department of Public Utilities State of New Jersey 101 Cornerce Street Newark, New Jersey 07102
Request for Additional Infomation SEP Topic VI-4 Oyster Creek. Unit 1 Docket No. 50-219 1-The following references represent the information being used for con-tainment isolation review:
Oyster Creek Nuclear Power Plant, Unit No.1, Facility Description a.
and Safety Analysis Report, Volume 1 b.
JCP&L letter of 12/14/79 in response to Bulletin No. 79-08.
c.
JCP&L letter of 4/10/80 in response to NUREG-0578 Implementation If the above documentation does not properly reflect the as-built condition, provide the necessary references.
2-Provide current P&ID drawings on the following systems which penetrate primary containment and are classified as essential or nonessential.
Essential a.
Emergency Condenser System b.
Control Rod Drive System c.
Core Spray System d.
Containment Spray System e.
Torus to Reactor Building Vacuum Breaker System Nonessential a.
Main Steam System b.
Feedwater System c.
Reactor Building Closed Cooling Water System l
l d.
Instrument Air System e.
Denineralized Water System f.
Reactor Clea.up System
---,-e e,
. g.
Shutdown Cooling System h.
Liquid Poison System 1.
Drywell Equipment Drain Tank
- j. Drywell Sump k.
Drywell and Torus Atmosphere Control Systems 1.
Reactor Recirculation Loop Sample System m.
Reactor Head Cooling System n.
Nitrogen System o.
Traversing In-Core Probe System 3-SRP Section 6.2.4. II.3.f states that scaled closed barriars may be used in place of automatic isolation valves, and should be under ad-ministrative control to assure that they cannot be inadvertently opened.
Sealed closed barriers include capped branch lines, test connections and vent lines.
Discuss the administrative controls applied to such barriers and note methods of administrative control.
l Examples as obtained from Reference lb include the following:
Ficure Valve Nos.
B (Isolation Condenser Return)
V-14-28 V-14-39 F (Shutdown Cooling Supply)
V-17-65 V-17-21 H (Cleanup Supply)
V-16-4 I (Cleanup Return)
V-16-65 J (Core Spray System)
V-20-42 l
V-20-44 l
P (Recirculation Loop Sample)
V-24-28 Q (Steam Line Drain)
V-1-137 S (Containment Spray)
V-6-134 V-6-136 I
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. Y (Vacuum Breakers & Associated Piping, Vent Pipe between Drywell ano Torus)
V-6-138 Z (Core Spray and Containment Spray Sup-ply From Torus)
V-20-29 4-Reference Ib provides a table of isolation infomation for systems which penetrate primary containment. This table indicates that valves V-20-21 V-20-41, V-2',-15 *nd V-21-18 are automatic isolation valves, however, no isolation signal code is provided. Provide the signals which are used to initiate these valves. This table also indicates that valves V-20-26 and Y-20-27 are remote manual valves and provides an isolation signal code.
Provide an explanation for this inconsistency.
5-Figure M of Reference Ib indicates that valve V-12-60 of the demineralized water system is closed in normal, shutdown and post accident conditfens.
Discuss the administrative controls applied to this system to assure tnat it cannot be inadvertently opened.
6-Provife current P&ID drawings of instrument lines penetrating the primary
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containment as noted in Reference 1b.
Indicate how these systems are pro-l vided with isolation provisions in accordance with Regulatory Guide 1.11.
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7-SRP Sections 6.2.4, II.3.b and c state that containnent isolation provisions for lines in engineered safety features or engineered safety feature-related systems as well as systems needed for safe shutdown of the plant may in-clude remote-manual valves, but provisions should be made to detect possible leakage from these lines outside containment. Discuss what provisions are provided for leakage detection from such systems, examples of which include the liquid poison system, shutdown cooling system, containment spray supply and core spray supply from the torus.
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