ML20137F983
| ML20137F983 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/22/1985 |
| From: | Donohew J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-85-07, GL-85-7, IEB-79-14, NUDOCS 8508270139 | |
| Download: ML20137F983 (12) | |
Text
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[M'[',g UNITED STATES 6
g NUCLEAR REGULATORY COMMISSION b .j WASHINGTON, D. C. 20555
%,,,,,# August 22, 1985 Docket No. 50-219 LICENSEES: GPU Nuclear Corporation Jersey Central Power and Light Company FACILITY: Oyster Creek Nuclear Generating Station
SUBJECT:
JULY 2,1985 MEETING WITH GPU NUCLEAR CORPORATION (GPUN) ON OYSTER CREEK NUCLEAR GENERATING STATI0f: TO DISCUSS CYCLE 11 REFUELING OUTAGE On Tuesday, July 2,1985, a meeting was held at NRC, Bethesda, Maryland with GPU Nuclear (GPUN), the licensee, on the Oyster Creek Cycle 11 Refueling Outage. This outage is scheduled to begin in April 1986.
Attachment 1 is the list of individuals that attended the meeting. The
% following is a summary of the significant items discussed and the actions, if any, taken or proposed.
1.0 Deferments from the Cycle 11 Refueling Outage to the Cycle 12 Refueling Outage Attachment 2 is a copy of a draft letter that GPUN handed out in the neeting. This draft letter includes a list of NRC requirements for proposed 1) defement from Cycle 11R outage to Cycle 12R outage and
- 2) cancellation and. scope change. In the draft letter, GPUN states that the Cycle 10M ' outage in October 1985 is to complete Environmental Qualification of Electric Equipment Important to Safety (10 CFP 50.49) and the Cycle 11R outage is to complete Appendix R Fire Protection.
GPUN stated that the Cycle 11R outage will be, with the deferments and cancellations, the second longest outage at Oyster Creek and the limitation of the outage will enhance GPUN's ability to manage the work presently planned for the outage.
The draft letter was discussed but no actions were proposed or taken.
2.0 Containrent LOCA Analysis Using a Drywell Temperature of 150"F GPUN provided a draft copy of its analysis of a Loss-of-Coolant Accident inside the drywell with the drywell at 150"F. An official copy will be submitted at the end of July with the Licensee Event Report (LER) on the drywell tenperature being above 135*F. The Containment Systen Branch, NRR, can begin its review of the higher drywell temperature with the draft report. A copy of the draft report is not attached to these meeting minutes because it will be submitted officially later.
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3.0 Integrated Living Schedule for Oyster Creek GPUN stated that it will address an integrated living schedule for Oyster Creek in its letter, discussed in Item 1.0 chove, on its proposed deferments crd cancellations of work now scheduled for the Cycle 11R outage. GPUN stated that they will also address this in its response to GL 85-07 which should be sent soon.
4.0 IE Bulletin 79-14 Reinpsection GPUN provided a copy of the Material Nonconformance Perorts, rarked-up support and iscretric drawings for Control Rod Drive Return, Liquid Poison, Main Steam, Core spray, Feedwater and Isolation Condenser Systen Piping which were generated during its recent IE Bulletin 79-14 reinspection efforts. These documents are tiot attached to these nreting minutes. These documents were submitted to the staff by letter from GPUN dated July 1, 1985.
Orisiaal signed by bd b 01 Jack N. Donohew, Jr., Project !!anager Operating Reactors Branch No. 5 Division of Licensing
Enclosures:
- 1. List of Attendees
- 2. Draft Letter cc: D. Crutchfield M.Laggart(GPUN)
DISTRI9UTION Docket File NRC PDR ORBf5 Reading JZwolinski CJamerson JDonohew OELD EJordan BGrimes ACRS (10)
NRC Participants DL:0PB#5 DL #5 DL:0R CJamerson b'JDonohew:tm JZwolinski i
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3.0 Integrated Livino Schedule for Oyster Creek GDUN stated that it will address an integrated living schedule for Oyster Creek in its letter, discussed in Item 1.0 above, on its proposed defements and ca'icellations of work now scheduled for the Cycle 11R outage. GPUN stated that they will also address this in its response to GL 85-07 which should be sent soon.
4.0 IE Bulletin 79-14 Ceinspection GPUN provided a copy of the Material Nonconformance Reports, marked-up support and isometric drawings for Control Rod Drive Return, Liquid Poison, Main Steam, Core spray, Feedwater and Isolation Condenser Systen Piping which were generated during its recent IE Bulletin 79-14 reinspection efforts. These documents are not attached to these meeting ninutes. These documents were submitted to the staff by letter from GPUN dated July 1, 1985.
N.
Alack N. Donohew, Jr., Project Manager Operating Reactors Branch No. 5 Division of Licensing
Enclosures:
- 1. List of Attendees
- 2. Draft Letter cc: D. Crutchfield M.Laggart(GPUN) o
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cc:
G. F. Trowbridge, Esquire Pesident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 1000 V Street, N.W. Post Office Box 445 Washington, D.C. 70036 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Libernan, Conk, et al. New Jersey Departnent of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey 07102 Eugene Fisher, Assistant Director Regional Administrator, Region I Division of Environmental Quality U.S. Nuclear Regulatory Commissine Department of Environmental 631 Park Avenue Protection King of Prussia, Pennsylvania 19406 380 Scotch Road Trenton, New Jersey 08628 BWR Licensing Manager P. B. Fiedler GPU Nuclear Vice President & Director 100 Interpace Parkway Oyster Creek Nuclear Generating Parsippany, New Jersey 07054 Station Post Office Box 388 Deputy Attorney General Forked River, New Jersey 08731 State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 D. G. Holland Licensing Manager Oyster Creek Nuclear Generating Station Post Office Box 388 Forked River, New Jersey 08731
ATTACHMEllT 1 MEETING WITH GPU NUCLEAR CORPORATION (GPUN) ON OYSTER CREEK NUCLEAR GENEPATING STATION TO DISCUSS CYCLE 11 REFUELING OUTAGE NAME ORGANIZATION J. Donohew NRC J. Zwolinski NRC
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J. Thorpe GPUN M. Laggart GPUN J. Chardos GPUN e
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M# GPU Nuclear Corporation "y
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, " Parsippany, New Jersey 07054-1149
, (201)263-6500
~ TELEX 136-482 Writer's Direct Dial Number:
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Mr. John Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Zwolinski:
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Subject:
Oyster Creek Nuclear Generating Station
' . Docket No. 50-219
~ Cycle 11 Refueling Outage We have recently completed the preliminary planning for work to be conducted ~
at Oyster Creek through the next refueling outage. The purpose of this letter is to review with you the results of that planning and to seek concurrence from the Staff on the proposed deferment of some regulatory items.
During your visit to'our office in April, we discussed with you and Mr. Donohew some very preliminary results of the outage planning efforts for Oyster Creek.
As our planning has now evolved, Oyster Creek will be shut down for a mini outage in approximately October of 1985 for completion of certain EQ modifica-tions, inspections, and other preliminary work leading to the major refueling outage. The refueling outage is now scheduled for a mid-April, 1986 start. In developing the refueling outage plan, we reviewed the total backlog of proposed plant modifications and major maintenance items. The development of the outage plan shows three or four large blocks of work which we feel are of high g priority. This includes completion of the Appendix R Fire Protection modifications - the largest single plant modification project; a series of activities to enhance the ability of the plant to be less susceptible to IGSCC; substantial work in the Control Room including computer hardware installation, and a number of other modifications throughout the plant. At the planning developed for the ' refueling outage, it became apparent the total proposed work scope was exceeding prudent manageability guidelines and would drive the planned outage duration to unacceptable limits, probably exceeding nine months.
The Company has spent several months, including reviews by senior management, in assessing this work scope growth in outage planning and has concluded, for a number of reasons identified below, the work scope must be restrained. In I
considering restraint of work scope, we have generally placed highest priority 1
GPU Nreat Corporation is a subsidra'ry of General Pubhc Utihties Corporation
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Mro. John'Zwolinski, Chief 1 .i Page Two
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on issues of providing maximum safety and operability return, providing maximum assurance of minimizing future IGSCC pipe cracking, and to reduce worker radiation exposure on a number of other major activities,. Even so, the ,
preliminary outage plan contemplates an outage length from potentially six to - l nine months long, a peak craft work force of 550 personnel, a total contractor l work force of approximately 800 and a projected total man rem exposure estimate of about 850. The planned work still consists of 30 total modification projects and a maintenance effort of over 3,000 individual items, including 110 major activities. We are continuing to assess ways of further reducing man rem exposure by adjusting detail work planning, further decontamination, and other techniques. Even with the proposed restraint in work scope, the next refueling outage for Oyster Creek is the second longest outage planned for the station, exceeded only by the refueling outage just completed. We believe the proposed ,
next refueling cycle work scope limitation will enhance our ability to manage the planned work through improved job supervision, minimize what might otherwise be unsafe congestion in the Control Room, Drywell and the 480V Switchgear Room and allow us to improve control of radiation exposure. There still remains an inherent risk of work scope growth during the outage because of a large numbe,r of detail inspectinns to be undertaken (recirculation loop piping, isolation condenser p.iping, reactor internals, reactor feedwater
, nozzles, etc.) which have the potential for requiring corrective action.
To contain work scope and improve manageability, we are seeking your -
concurrence for the deferment of several regulatory related modifications. In
. - some cases, we are suggesting deferment of the completion of these modifica-tions until the following operating or refueling cycle and in other cases, we believe prudent technical arguments exist for the permanent cancellation of the modification. Attachment I to this letter contains a listing of those modifications which we believe can be deferred until the following operating or refueling cycle. Our assessment of these seven items is that no significant safety risk is involved. In one case, i.e., item one of the attachment, the deferment reflects substantial technical difficulties in the ability of our subcontractor to deliver completed software. Attachment 2 to this letter identifies those regulatory items which we believe scope adjustments or cancellations are technically justified. For those items reflecting scope adjustment, we would still accomplish the revised scope during the next refueling outage. In many cases, for proposed cancellation items, preliminary discussions have already occurred with the Staff, and we are preparing technical submittals on each of the items to further support the reasonableness for cancellation. These submittals will be forwarded to you beginning very shortly and extending over the next two to three months. In the event we cannot come to final closure with the Staff on the issue of cancellation, we would propose deferment until the following refueling outage to allow our outage planning to stabilize.
Mr.. John ~Zwolinski, Chief
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) If you shoulo have any questions concerning this correspondence and the attachments, please contact Mr.' M. W. Laggart, Manager, BWR Licensing at (201) 299-2341. "
1 Very truly yours, R. F. Wilson Vice President and Director Technical Functions RFW/al ATT cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406 .
NRC Resideint Inspector
, Oyster Creek Nuclear Generating Station -
l Forked River, N.J. 08731
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Attachment I '
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Items for Deferment a i .
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1.' Safety Parameter Display 6 tem M . ware (NUREG 0737 Supplement 1) i
- The Safety Parameter Display System (SPDS) hardware is scheduled to be installed during the Cycle ~ 11 refueling outage. Although SPDS hardware installation is expected to be completed during the outage, delays in delivery of vendor-provided hardware and software preclude making SPDS fully operational until during the operating cycle after the outage.
- 2. Isolation Condenser Makeup Pump As a result of SEP Topics II-3.B. II-3.B.1, II-3.C, and III-4.A. GPUN consnitted to provide a protected means from a protected water supply to supply makeup to the Isolation Condenser shells for decay heat removal in the event flooding conditions or tornado missiles render the normal makeup sources inoperable. Makeup is currently provioed by the Condensate Transfer System with the Fire Protection Water System as the normal backup. In addition, the Demineralized Water System can be utilized to provide makeup via a temporary hose interconnection. The reliability afforded by one primary and two backup makeup sources makes it unlikely that all of these sources would be rendered inoperable. The protected makeup method will be provided during operating Cycle 11 t
subsequent to the refueling outage and deferral is requested.
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- 3. Intake Canal Level Instrumentation An automatic water level instrument with remote readout was scheduled for installation during the Cycle 11 refueling outage. This_ modification is -
in response to SEP Topics II-3.B. II-3.B.1 and II-3.C per IPSAR Section 4.1. We propose to defer this installation until operating Cycle 11 subsequent to the refueling outage.
Intake canal level is monitored at least once per eight hour shift and this inspection practice is formalized in the shift turnover procedure.
The above inspection is adequate until installation of the level instrument is complete. In addition, the dramatic weather conditions which cause extremes in intake canal water level would provide an obvious c indication to surveil the intake water level closely.
- 4. Masonry Walls (IE Bulletin 80-11)
A partial deferment is requested for all walls that do not require the plant to be shut down to be accomplished. For all walls requiring plant shutdown, installation will be completed during the Cycle 11 refueling outage. It is our intent to complete the modifications during operating Cycle 11; however, if unanticipated operational safety. concerns inhibit some aspect of the modifications, they will be completed during the Cycle 12 refueling outage. The wall failure consequence analysis previously submitted by GPUN letters dated March 14 and May 11, 1984 has shown that wall failures will not jeopardize the safe shutdown of the facility.
This deferment aoes not apply to required submittals that will be provided on the agreed upon schedule.
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) 5. Torus Attached Piping Supports ?.
The objectives of the Mark 1 Containment Long Term Program we're to ,
, establish conservative design basis loads that are appropriate for the anticipated life of the plant and to restore the originally intended t
- design safety margins for the containment system.. The current design margins for torus attached piping have been found to be adequate to ensure system integrity for all loading conditions, even though they do not fully meet the original design margins. The Long Term Program identified piping supports and reinforcing saddles which are to be added and existing supports which are to be modified to increase the design safety margins. Piping system support modifications requiring a shutdown will be accomplished during the Cycle 11 refueling outage. Due to work load considerations, the remaining piping support modifications will be installed during the operating cycle subsequent to the Cycle 11 refueling outage; however, if unanticipated operational safety concerns inhibit some aspect of the modifications, they will be completed during the Cycle 12 refueling outage. By Order dated January 19, 1982, Torus Attached Piping modifications are currently required to be completed prior to startup from the Cycle 11 refueling outage. As discussed above, we request that a portion of these modifications be deferred.to the following operat.ing cycle; . .
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- 6. Torus Bulk Temperature Indication (Mark 1 Program - NUREG 0661/0783) i
' NRC Order dated January 19, 1982 requires Torus bulk temperature indication in accordance with Mark 1 Program requirements to be provided' prior to startup from the Cycle 11 refueling outage. In addition, we committed to meet Regulatory Guide 1.97 Torus Bulk Temperature
- requirements durina the Cycle 11 refueling outage. We propose to defer the upgrade of Torus temperature indication until the Cycle 12 refueling i- outage. We believe the Mark I requirements to be excessive from a i technical point of view. Currently, Torus' water temperature is monitored
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by four (4) thermocouples situated in pairs diametrically opposed. We are evaluating the repositioning of one thermocouple of each pair to an j existing thermowell such that there is one thermocouple every 90'.
The methodology previously submitted to evaluate the adequacy of the setpoints for unbypassed thermal overloads (TOL) was based on the then prevalent practice at OCNGS of setting the torque switches. This l practice was based on restricting the valve seating current to within 120 to 200% of rated motor full load current. However, by the end of 1984, GPUN had implemented and completed a new approach on the M0V torque switch settings. This approach is based on the Motor-0perated Valve Analysis and Test System (M0 VATS) method of valve testing, wherein a valve's actual thrust output is recorded. The acceptable setting for a
! torque switch is the one which produces a thrust greater than the minimum
! required thrust for the valve's safety function. As a result, a new t
methodology was developed to reflect this change.
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.i Tha newly developed meth.oqology is based on MOV motor winding thermal
.- g limits. This informatfo'n is obtained from the motor characteristic I
/ curves supplied by the' valve vendor. GPUN has requested this information and is waiting for the supplier to comply. ,
It was also revealed that in order to install some of the new TOL heaters, the ESF valve circuits have to be de-energized thus requiring a plant shutdown. However, the majority of the new TOL heaters can be installed without plant shutdown. Therefore, approximately 70% the modifications required will be accomplished during the next opt ing, cycle (Cycle 11) and the remainder will be accomplished during tne Cycle 12 refueling outage.
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Attachment 2 '
, Items fh dancellation or Scope Change I
- 1. Feedwater Nozzle Internal Inspection (NUREG 0619) - Scope Change - We would perform the external UT inspection of the feedwater nozzles next refueling outage, however, we would,not plcn on proceeding with internal PT inspections. We believe the external UT inspection will substantiate lack of significant nozzle cracking.
- 2. Containment Vent and Purge Valve Replacement (NUREG 0737) - Cancellation
- 3. Containment Isolation Signals to Vent and Purge Valves on Containment High Radiation (NUREG 0737) - Cancellation
- 4. Isolation Condenser High Point Vents (10CFR50.44) - Cancellation
- 5. Recirculation Loop Interlock (NUREG 0737) - Scope Change - The recirculation loop interlock had been planned as a fully automatic interlock so that the operator could not isolate the five recirculation loops. We proposed to proceed with the modification at the next refueling outage, but the design is being modified toward operator alarm interaction rather than'being totally automatic.
- 6. Torus Thermal' Mixing (Mark l Program - NUREG 0661) - Cancellation
- 7. Torus Local Temperature Indication (Mark 1 Program - NUREG 0661/0783) - -
) Cancellation - Based on endorsement of BWR Owner's Group position
_ contained in GE Report NE00-30832.
- 8. Drywell Temperature Monitoring and Instrument Air Transaitters - Part of Reg. Guide 1.97'- Cancellation - (Items A.6 and D.25 of Table 3 GPUN letter dated June 13, 1984 - Reg. Guide 1.97 response) l
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