ML20198N913
| ML20198N913 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Oyster Creek |
| Issue date: | 08/14/1985 |
| From: | Sheron B Office of Nuclear Reactor Regulation |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20151H203 | List:
|
| References | |
| FOIA-86-26 TAC-59342, NUDOCS 8606060200 | |
| Download: ML20198N913 (2) | |
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MEMORANDUM FOR: John Zwolinski, Chief, Operating Reactors Branch #5, DL
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Brian Sheron, Chief, Reactor Systems Branch, DSI
SUBJECT:
QUESTIONS CONCERNING OYSTER CREEK ISOLATION CONDENSER VENT EXEMPTION REQUEST Plant Name:
'0yster Creek Docket Number:
50-219 TAC Number:
59342 Licensing Stage:
Operating Reactor Responsible Branch: ORBS Project Manager:
Jack Donohew Review Branch:
Reactor Systems Branch Review Status:
Awaiting Information The Reactor Systems Branch is reviewing a GPU nuclear request for exemption to the requirement for a vent on the isolation condensers at Oyster Creek. We need answers to the enclosed questions before we.can complete our review.
P Brian Sheron, Chief Reactor Systems Branch Division of Systems Integration
Enclosure:
As stated cc:
R. Houston D. Crutchfield J. Donohew
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W. Hodges
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QUESTIONS ON OYSTER CREEK EXEMPTION REQUEST 1.
The analysis in Attachment II to the July 23, 1985 exemption request is incomplete.
Low pressure systems are always assumed to be available in the analysis, provided the reactor can be depressurized.
Other events which result in hydrogen generation plus the need for the isolation condensers may be postulated.
One example of such an event would involve a LOCA with core damage followed by isolation of the break and a loss of low pressure systems (CRD and feedwater also not available).
In order to adequately assess the impact of isolation condenser venting versus no venting, the full spectrum of events requiring isolation condenser venting must be analyzed. Please provide these additional analyses.
t 2.
Are there any negative safety implications to adding isolation condencer vents?
3.
Will the installation of isolation enndenser vents involve a significant increase in radiation exposure for workers?
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<* n LICENSE AUTHORITY FR.E COP.)
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Mr. P. B. Fiedler Vice President & Director Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
Dear Mr. Fiedler:
SUBJECT:
ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES (GENERIC LETTERS 82-05 AND 82-10)
Oyster Creek Nuclear Generating Station The Commission has issued the enclosed Order confirming your comitments to implement those post-TMI related items set forth in NUREG-0737 for which the
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staff requested completion on or after July 1,1981. This Order is based on commitments contained in your letters responding to the NRC's Generic Letters 82-05 and 82-10 dated March 17, 1982 and May 5,1982, respectively.
The Order references your letters and, in its Attachments, contains lists of the applicable NUREG-0737 items with your schedular commitments. As discussed in the Order, several of the items listed in Generic Letter 82-10 will be handled outside of this Order.
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The Commission's intention when it issued NUREG-0737 was that items would be completed in accordance with the staff's recommended schedule. However, our evaluation of your proposed schedule exceptions. concludes thac the proposed delays are acceptable. Among other things, the Order requires implementation of these items in accordance with your proposed schedule.
Some of the items set forth in the A'ttachments to the Order are subject to post
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implementation review and inspection. Our post implementation review and/or the development of Technical Specifications may identify alterations to your method of implementing and maintaining the requirements. Any identified alter-ations will be the subject of future. correspondence.
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14r. P. B. Fiedler I4 arch 14, 1983 A copy of this Order is being filed with the Office of the Federal Register for publication.
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Sincerely, gg 15 Dennis M. Crutch ield Chief Operating Reactors Branch #5 Division of Licensing 1
Enclosure:
Order cc w/ enclosure:
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Mr. P. B. Fiedler tiarch 14, 1933 CC G. F. Trowbridge, Esquire -
Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U. S. KRC 1800 M Street, N. W.
Post Office Box 445
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Washington, D. C.
20036 Forked River, New Jersey 08731
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J. B. Lieberman, Esquire Commissioner Berlack, Israels & Lieberman New Jersey Department of Energy 26 Broadway 101 Commerce Street New York, New York 10004 Newark, New Jersey 07.102 Ronald C. Haynes, Regional Administrator Nuclear Regulatory Cemnission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
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J. Knubel SWR Licensing Manager GPU Nuclear 100 Interplace Parkway Parsippany,' New Jersey 07054
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Deputy Attorney General State of New Jersey Department of Law. and Public Safety 4
36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township
.818 Lacey Road Forked River, New Jersey 08731 O. S. Environmental Protection
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Agency Region II Office
,7 ATTN:
Regional Radiation Representative 26 Federal Plaza New York, New York 10007 '
Licensing Supervisor Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
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UNITED STATES OF AMERICA
- HUCLEAR REGULATORY COMMISSION In the Matter of
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GPU NUCLEAR CORPORATION AND JERSEY
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CENTRAL POWER AND LIGHT COMPANY
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Docket No. 50-219
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(0yster Creek Nuclear Generating
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ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES I.
GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) are the holders of Provisional Operating License No. OPR-16 which authorizes the operation of the Oyster Creek Nuclear Generating Station (the facility) at steady-state reactor power levels not in excess of 1930 megawatts thermal. The facility consists of a boiling water reactor (BWR) located in Ocean County, New Jersey.
II.
Following the accident at Three Mile Island Unit No. 2 (TMI-2) on March 28, 1979, the Nuclear Regulatory Commission (NRC) staff developed a number of
.w proposed requirements to be implemented on operating reactors and on plants under construction. These requirements include Operational Safety, Siting and Design, and Emergency Preparedness and are intended to provide substantial additional protection in'the operation of nuclear facilities based on the
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(7590-01) experier:e from the accident at TMI-2 and the off.icial studies and investic nions of the accident. The staff's proposed requirements and schedule for implementation are set forth in NUREG-0737, " Clarification of TMI Action Plan Requirements." Among these requirements are a number of items, consisting of hardware modifications, administrative procedure implementation and specific information to be submitted by the licensee, scheduled to be completed on or after July 1,1981. On March 17, 1982,
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a letter (Generic Letter 82-05) was sent to all licensees of operating power reactors for those items that were scheduled to be implemented from July 1,1981 thrcugh March 1,1982. Subsequent 1y on May 5,1982, a letter (Generic Letter 82-10) was also sent to all licensees of operating power reactors for those items that were scheduled for implementatiun after March 1,1982. These letters are hereby incorporated by reference.
In these letters each licensee was requested to furnish within 30 days pursuant to 10 CFR 50.54(f) the following information for items which the staff has proposed for completion on or after July 1,1981:
(i) For applicable items that have been c'ompleted, confirmation cf ccmpletion and the date of completion, (2) For items that have not been completed, a specific' schedule for implementation, which the licensee committed to meet, and (3) Justificaticn for delay, demonstration of need for the proposed schedule, and a description of the interim compensatory ceasures being taken.
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III.
GPU Nuclear Corporation responded to the Generic Letter 82-05 by letters dated April 20 and June 15, 1982 and February 18, 1983. GPU Nuclear Corporation responded to the Generic Letter 82-10 by letters dated October 8 and 19,19.82 and January 7,1983.
I.n these submittals, GPU Nuclear Corporation confirmed that some of the items identified in the Generic Letters had been completed and made firm commitments to complete the remainder. The attached Tables summarizing the licensee's schedular commitments or status were developed by the staff from the Generic Letters and the licensee-provided information.
Generic Letters 82-05 and 82-10 applied to fourteen and ten items respectively.
O' the fourteen items listed in Generic Letter 82-05, two items are not included in this Order. You have requested that implementation of, item II.B.3,
" Post Accident Sampling," be deferred until the Cycle 11 refueling / maintenance outage. We believe that postponement of equipment installation beyond the Cycle 10 outage is not in the best interest of a sound emergency response position. Therefore item II.B.3 will be removed from this Order and its disposition will be determined under a separate licensing action.
In addition,
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you have also taken the. position that item II.E.4.2(7), " Isolate Purge and Vent Valves on Radiation Signal," is not applicable to the Oyster Creek Plant. We
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do 'not concur with this conclusion and therefore, item II.E.4.2(7) will be removed from this Order and disposition will be determined under separate licensing action.
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'l (759G-01) 4 There are several items in Generic Letter 82-10 that, as noted in Attachment 2, have licensee sghedules which are yet to be determined. These items are therefore not included in this Order. The licensee considers some of the -
items addressed in this Order to be completed or to require no modifications.
These items are so noted in Attachments 1 and 2.
The staff's evaluation of the licensee's delays for implementation of the remaining items is provided herein.
II.B.2 Plant Shielding This item is complete with the exception of tie-in for the Standby Gas Treatment System (SBGTS). The SBGTS modifications will be completed during e
the present refueling outage (Cycle 10) which began February 12, 1983. This tie-in could only be accomplisheo during a refueling outage.
During the interim there were two trains of SBGT, and in the event one filter train became saturated, the redundant train would have been available.
II.F.1 Accident Monitoring (1-6)
A plant shutdown is required to accomplish the modifications. The current refueling outage which began on February 12, 19'83 is the first available
.1 outage of sufficient duration which,h_as occurred since the issuance of NUREG-0737.
Items II.F.1.1, 2, 4, 5 and 6 will be completed during the Cycle 10 refueling outage. For II.F.1.1, 4, 5 and 6 there are existing monitors, however, the instruments ranges are not as specified in NUREG-0737.
The licensee believes that these monitors would be acceptable for all but the i
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most severe accidents. Emergency response recommendations to local agencies would be based on other plant parameters and inputs from offsite monitoring teams. For II.F.1.2 the licensee states that presently there are charcoal -
filters in the stack gas monitoring system, however, for severe accidents they would not be accessible due to high radiation levels.
In such cases the recommendations to local agencies would be accomplished based upon other plant parameters and inputs from offsite mon.itoring teams. For item II.F.1.3 completion can only be accomplished during a refueling outage and it has been deferred to the Cycle 11 outage because of the magnitude of the work scheduled for the present outage. The licensee has stated that there are other methods for detecting a major accident within containment such as high drywell pressure, c
low reactor water level, torus water level, and neutron monitoring.
II.K.3.19 Interlock of Recirculation Pump Completion of this item can only be accomplished during a refueling outage and it has been deferred to the Cycle 11 outage because of the magnitude of the work scheduled for the present outage.
The Oyster Creek Technical Specifications (TS) safety limits require that at least two recirculation. loop. suction,. valves and their associated discharge valves be in the full open position. This requirement is also addressed in
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ths plant operating procedures, and in addition, the licensee has' installed hinged covers over each valve operating switch which serves as a warning to the operator not to violate the requirement.
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6-ke find, based on the' above-evaluation, that (1) the licensee has taken corrective actions.regarding the delays and has made a responsitile effort to implement the NUREG-0737 requirements noted; (2) there is good cause for the several delays (unexpected design complexity, interface problems, and eqisip-ment delays); and (3) as noted above, interim compensatory measures have been provided.
In view of the foregoing, I have determined that these modifications and actions are required in the interest of public health and safety, and there-fore the licensee's commitments should be confirmed by Order.
IV.
J Accordingly, ptrsuant to Sections 103,1611, and 161o of -the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED EFFECTIVE IMMEDIATELY THAT the licensees shall:
Implement and maintain the specific items described in the Attachments to this Order in the manner described in the licensee's submittals noted in Section III' herein no later
.1 than the dates in the Attachmen.ts.
The licensees may request a hearing on this Order within 20 days of the date of publication of this Order in the Federal Register. A request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C.
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A copy shall ~also be sent to the Executive Legal Director at the same address. A REQUEST FOR HEARING SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS 0F THIS ORDER.
If a hearing is requested by the licensees, the Commission will issue an Order designating the time and place of any such hearing.
If a hearing is held concerning this Order, the issue to be considered at the hearing shall be whether, the licensee should comply with the require-ments set forth in Section IV of this Order.
This Order is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Dated at Bethesda,archMaryland, this 14 day of h 1983.
Attachments:
l.
Licensee's Cocmitments on Applicable NUREG-0737 Requirements.from Gen.eric Letter 82-05 2.
Licensee's Commitments on Applicable NUREG-0737 Requirements from Generic Letter 82-10 e
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.O 0YST O EEK Attacim% 1 LICENSEE'SCditIITNENTSONAPPLICABLENL
.-0737ITEMSFROMGENElkICLETTER82-05
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NUREG-0737 Liccnsec's Completisin Itcm Title Schedule Requirement Schedule (or staly.),',,
li.K.3.19 Interlock on Recirculation 07/01/01 Insta'll interl'ocks on Refueling outage !! (4-l;5)
Pumps recirculation pump loops I
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!!.K.3.27 Connon Reference Level 07/01/01 Provide coninon reference Complete ;
invel for vessel level instrumentation l
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'Where completion,date refers to a refueling outage (the estimated date wiien ti;a outage begins), the item will be completed prior to the restart of the facility n
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LICENSEE'S C0ftllTMENTS ON APPLICABLE If
-0737 ITEMS FROM GENERIC LCTTER 82-10
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Licensec's Cumpletion NUREG-0737 Schedule (or statur.)*
Schedule Requirement Item Titic 10/01/82 pdr Revise administrative procc-Completc
!.A.l.3.1 Limit Overtime Gen Ltr: fl2 :12: durcs to limit overtime'in accordance w/NRC Policy l
dtd.,6/15/82 Statement issued by Generic, Ltr. No. 82-12, dtd 6/15/82
!1.A.I.3.2
- Minimum Shift Crew To be' super-To be addressed.in the Final To be addressed when final j_
seded by Pro-Rule on Licensed Operator Rule is, issued.
i posed Rule Staffing at Nuclear Power Units l.l.C.1
- Revise Emergency Superseded by Reference SECY 82-111, To be determined Procedures SECY 82-111 Requirements for Emergency j
Response Capability
,,js Submit ;lant specific reports Complete l111.D.1.2 RV and SV Test Programs 04/01/82 on relief valve and safety valve p,rogram,
! II.K.3.18 ADS Actuation 09/30/82 Submit revised position on Completc i
_need far modifi.c_atjans.
l Submit plant specific analyses To be determined.following II.K.3.30 & 31
- SOLOCA Analysis 1 year staff approval of model after staff approval of model III.A.l.2
- Staffing Levels for Superseded by Reference SECY 82-111, To be Determined Emergency Situations82-111 Requirements for Emergency Response Capability III.A.l.2
- Upgrade Emergency Support Facilities
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llI.A.2.2
- Meteorological Data III.D.3.4 Control Room Habitability To be deter-Modify facility as identified Refueling outage 11 (4-05) -
mined by by licensee study.
licensee
~*Where completion date refers to a, refueling outage (the estimated date ivhen tIie outage begins), the item will be completed prior to the restart of the. facility.,
- ANot Part of Conf,irmatory Order.
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AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 81 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated April 22,1985, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act),
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and the sComission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the-Comission; C.
Thsreisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's 'regulatiens; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and r
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by changing the schedule i Confirmatory Order dated June 17, 1983, for when the NUREG-0737. Item II.B.3, Post-Accident Sampling System is to be fully operational.
This date will be the next shutdown of known sufficient duration to draw samples from the Reactor Recirculation System, Liquid Poison System and Shutdown Cooling System but no later than the restart from the planned outage currently scheduled for October 1985 or the Cycle 11 refueling outage, whichever is earlier.
3.
This license amendment is effective as of the date of its issuance.
eFOR THE NUCLEAR REGULATORY COMMISSION lp af6. 4.. 8 I
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./ John A. Zwolinski, Chief Operating Reactors Branch 15 8
Division of Licensing
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Date of Issuance:
April 29.1985.
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