ML20052D126
| ML20052D126 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/28/1982 |
| From: | Broehl D PORTLAND GENERAL ELECTRIC CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-TM GL-82-05, GL-82-5, TAC-44482, TAC-44553, TAC-44696, TAC-44735, TAC-44892, TAC-44963, TAC-45034, TAC-45105, TAC-47642, TAC-47713, TAC-47784, TAC-47981, NUDOCS 8205060297 | |
| Download: ML20052D126 (6) | |
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.k 15h April 28, 1982 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Eisenhut:
TROJAN NUCLEAR PLANT Additional Information Regarding NUREG-0737 In Response to NRC Generic Letter 82-05 provides supplemental information regarding implementation schedules of NUREG-0737 TMI Action Items in response to NRC Generic Letter 82-05.
All but four of the Action Items listed in Enclosure 1 of NRC Generic Letter 82-05 were completed at Trojan in accordance with NUREG-0737 4
schedules. The four Action Items not completed by January 1,1982 are:
II.B.3, Post-Accident Sampling; II.F.1.1, Effluent Noble Gas Radiation Monitors; II.F.1.2, Effluent Iodine and Particulate Monitors; and II.F.1.6, Containment llydrogen Monitors. The anticipated difficulty in completing these Action Items by the implementation date of January 1, 1982 was identified and reported to the NRC by PGE on October 21, 1981 (Attachment-2). At that time, a request for schedule extension, together with justification for an extension and compensatory measures in the I
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interim, was submitted to the NRC.
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.c Concerted efforts have been made for completion of these Action Items.
j g liowever, due to additional difficulties in vendor design development and I
equipment manufacturing, which could not be foreseen and which are not under our control, the implementation schedules for Action Items II.B.3, II.F.1.1 and II.F.1.2 have to be extended until July 1, 1983.
Best efforts will continue to be applied to install these items as soon as possible.
A description of the vendor delays justifying these extensions is dis-cussed in Attachment 1.
The main steam line radiation monitors (part of II.F.1.1) and the Containment hydrogen monitors (II.F.1.6), listed 8205060297 820428 PDR ADOCK 05000344 p
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Mr. D. G. Eisenhut i
April 28, 1982 Page two l
in Enclosure 1 to the NRC Generic Letter 82-05, a:e expected to be complete by August 1, 1982. Necessary equipment for these two Action l
Items is onsite and construction is in progress.
If it appears that the l
August 1, 1982 completion date will not be met, the NRC will be informed
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promptly.
Sincerely, j!
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Subscribed and sworn to before me this 28th day of April 1982.
&Y <v W$, J Notfr~yPublicofOregon My Commission Expires:
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Mr. Robert A. Clark Operating Reactors Branch No. 3 Nuclear Regulatory Commission Mr. Lynn Frank State of Oregon Department of Energy
Trojnn Nuclear Plent D. C. Eisenhut Docket 50-344 April 28, 1982 License NPF-1 Page 1 of 4 TROJAN NUCLEAR PLANT ADDITIONAL INFORMATION REGARDING NUREG-0737 IN RESPONSE TO NRC GENERIC LETTER 82-05 4
1.
Action Item I.A.3.1 - Simulator Examinations
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On August 7, 1981 th'e NRC issued Generic Letter 81-29 requesting information on the scheduled simulator exams in 1981 and 1982.
PGE responded to the Generic Letter on October 1,1981, committing to include the NRC simulator exam in the licensing examina* ion for the Trojan Reactor Operators (R0s) and Senior Reactor Operators (SR0s).
The PGE letter also discussed the scheduled NRC simulator exams in February and December, 1982.
The first simulator exam in 1982 was conducted on February 13,1982 by the NRC as scheduled. The next NRC simulator exam is expected in December, 1982 for the Trojan R0s and SR0s.
2.
Action Item II.B.2 - Plant Shielding The Plant shielding review conducted at Trojan resulted in the following four areas of modifications:
Installation of valve reach rods for draining the -radioactive a.
waste gas decay tank and installation of steel plate shic1' ding for the waste gas surge tank cubicle.
b.
Installation of shielding for CVCS letdown lines and holdup tanks to permit access at the radwaste control panel.
c.
Installation of reach rods for Residual Heat Removal System letdown valves.
d.
Modification to facilitate remote handling of contaminated filters.
All modifications were completed before January 1, 1982.
3.
Action Item II.B.3 - Post-Accident Sampling PGE's letter of October 1, 1981 (Attachment 2) described the efforts made in system design and vendor seicetion for major equipment and requested an extension in the implementation schedule until August 1, 1982 due to equipment unavailability. This implementation schedule was based on the equipment delivery schedule of January 1, 1982 which was provided at that time by the equipment vendor.
In order to expedite design and manufacturing of the sampling system, PGE provided engineering assistance at the vendor's facility to help resolve detailed design. PGE also took over design and fabrication j-responsibilities for certain portions of the equipment to expedite completion of the major components by the vendor.
In spite of the I
engineering support and assistance provided by PCE, the vendor's schedules have continued to slip. According to the vendor, delivery.
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Trojan Nuclecr Plant D. G. Eisenhut Docket 50-344 April 28, 1982
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License NPF-1 Page 2 of 4 of the PASS equipment to Trojan is now expected for August 15, 1982.
Due to vendor. schedule problems,'we have requested assistance from Bechtel Power Corporation to act as our agent and to supervise and expedite completion of the engineering by the vendor. Considering the schedule slipages, the required installation time of approxi-mately 12 weeks and necessary training of Plant personnel, we anticipate that the PASS system may be completed and operational in 1982. However, realistic allowance for further schedule slippages beyond our control, and allowance for installation and testing prob-lems could defer complete implementation until July 1,1983.
In the interim, PGE will maintain implementation of the post-accident sampling procedure outlined in Item 2.1.8.a of PGE's submittal of April 15, 1980 (Page 14 of the Attachment) to the NRC.
This interim procedure was reviewed and approved by the NRC letter of April 23, 1980 transmitting a safety evaluation of the TMI Short-Term Actions at Trojan.
4.
Action Item II.B.4 - Training for Mitigating Core Damage A training program reviewing the use of the installed systems to control or mitigate a core damage accident were developed and provided to Shif t Technical Advisors and to operating personnel, from the Trojan General Manager, to the Operations team,'to the licensed operators. The training program was completed before h
October 1,1981 as required in NUREG-0737.
5.
Action Item II.E.1.2 - Auxiliary Feedwater System Initiation and Flow Indication Automatic initiation of the AFW System at Trojan is provided by the Eningecred Safety Feature actuation system.
Thus, no modifica-tions were required.
Modifications to upgrade the AFW System flow indication to the safety grade indication as specified in NUREG-0737 were completed before January 1, 1982.
6.
Action II.E.4.2 - Containment Isolation Dependability As committed in the PGE letter of July 17, 1981 to the NRC, reduction of the Containment pressure setpoint for Containment isolation was completed in September, 1981.
The Hydrogen Vent System isolation valves at Trojan now receive a high-radiation signal for automatic isolation in accordance with NUREC-073 7.
Inclusion of the high-radiation signal into isolation of the hydrogen vent valves was completed before January 1,1982.
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Trojen Nuclear Plant D. G. Eisenhut Docket 50-344 April 28, 1982 License NPF-1 Attachment I l
Page 3 of 4 7.
Action Item II.F.1.1 - High-Range Effluent Radiation Monitors PGE's letter of October 21, 1981 (Attachment 2) discussed the design effort made for the main steam line radiation monitoring system and justification for extension of the implementation schedule until August 1, 1982. Since then, selection of the vendor for the radiation monitors was completed and the purchase order issued in October,1981. The final design details have been com-pleted and issued to the field for construction. The detectors, shicids and associated readout equipment have been received recently and the construction is scheduled to commence in mid-April.
It is presently expected that the main steam radiation monitors will be in service by August 1,1982.
PCE's letter of October 21, 1981 also discussed difficulties for meeting the completion date of January 1, 1982 for other high-range effluent radiation monitors and requested extension of the implemen-tation date until August 1, 1982. The request for extension was primarily due to design changes to integrate the E' fluent Noble Gas Monitoring System into the Action Iter II.F.1.2 Effluent Iodine and Particulate Monitoring System, as discussed in detail in Attachment 2.
However, despite repeated and concerted etiorts by PGE to expedite system design and equipment delivery to meet the August 1, 1982 implementation date, the equipment vendor, has continued to slip the scheduled milestones. All electrical drawings scheduled for delivery in January 1982 have not been received, nor have the majority of the mechanical drawings.
It is our best estimate that equipment will not be shipped until. August 1982, which is 7 months behind the original-schedule. According to the vendor, the schedule slippage is due to extensive backlogs in equipment order by other nuclear plants and lack of necessary manpower. Assuming equipment delivery in August 1982 and an estimated installation time of 8 weeks, it is presently-anticipated that the installation may be completed in 1982. However, any additional delay in equipment delivery will result in a day-for-day delay in completion beyond 1982. Realistic allowances for further schedule slippages beyond our control and allowances for installation and testing problems could defer complete implementation until July 1, 1983.
As stated in PCE's letter of October 21, 1982, until completion of the monitoring system, PGE will maintain implementation of the grab 4
sample procedures described in Page 29 (Item 2.1.8.b, Section B) of-i PCE's letter to the NRC dated January 2, 1980. This procedure was reviewed and approved by the NRC Ictter of April 23, 1980 for interim use at Trojan.
8.; Action Item II.F.1.2 - Effluent Iodine and Particulate Monitoring System See Item 7 (Action Item II.F.1.1) above for discussion of equipment delivery problems.
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Trojan Nuclear Plant D. G. Eisenhut-Docket 50-344 April 28, 1982 License NPF-1 Page 4 of 4 19.
Action Item II.F.1.3 - Containment Area Radiation Monitors Installation of the Containment high-range area radiation monitors was completed before January 1, 1982.
10.
Action Item II.F.1.4 - Containment Pressure Indication The Containment high-range pressure indicating system, consisting of two indicator / recorders, was installed at Trojan before January 1, 1982.
11.
Action II.F.1.5 - Containment Water Level Indication i
Installation of the Containment water level indicators (wide-range and narrow-range) was completed before January 1, 1982. As dis-cussed in PCE's letter of July 17, 1981, the measurement range of the wide-range indicators will be expanded during the 1982 refueling outage to cover 200 inches in accordance with NUREG-0737.
12.
Action Item II.F.1.6 - Containment Hydrogen Monitors PCE letters of October 21 and December 28, 1981 to the NRC provided
- a. design description of the Containment hydrogen monitors, difficul-ties experienced for completion of the system in 1981, and a request for implementation schedule extension until August 1, 1982. The PGE letter also provided a description of compensatory measures being taken in the interim. The schedule delay was primarily due to a change in direction to replace the existing hydrogen monitoring system with a new, qualified hydrogen monitoring system.
The new environmentally qualified monitoring system has been received.
at Trojan. The engineering detailed design has been completed and installation is in progress. The Containment Hydrogen Monitoring i
System will be completed by August 1, 1982.
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D. C. Eisenhut Troj an Nuclear Plant-Dock 2t 50-344 April 28, 1982 License NPF-1 M
Page 1 of 7 I_
e C{ Portland General Electric Company f-October 21, 1981 im D Wes W.e Prese1 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. Darrell C. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Co= mission Washington, DC 20555
Dear Mr. Eisenhut:
Attached is supplemental information regarding implementation status of some of the post-TMI NRC requirements in NUREC-0737. Attach =ent 1 provides current status of implementation for five Action Items (Items II.B.3, II.F.1.1,.II.F.1.2 II.F.1.6, and II.F.2) which have a preliminary indication of anticipated delays in their completion.
A description of the scope of implementation for Action Item II.F.1.2 is also included in Attachment 1. updates implementation status of four Action Items (Items II.D.1.2, II.K.3.1, II.K.3.5, and III.A.2).
We are making a concerted effort to meet the required implementation l
dates for the TMI Action Items. A great deal of extra effort is being made to complete the design, procurement, and installation of the five Action Items discussed in Attachment 1.
However, due to circumstances that could not be foreseen and which are not under our control, diffi-culty in meeting the January 1, 1982 deadline is anticipated for these items. It is currently expected that these Action Items will be com-pleted by August 1, 1982. A description of expected schedule difficul-ties, together with alternate means of complying with NRC requirements on an interim basis and the proposed schedule changes, is discussed in.
Sincerely, f
Bart D. Withers Vice President Nuclear y /KM[4sh2A14
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Mr. Robert A. Clark Nuclear Regulatory Commission Operating Reactors Branch No. 3 Mr. Lynn Frank State of Oregon Department of Energy hdo 4
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D. G. Eisenhut Docket 50-344 April 28, 1982 License HPF-1 Page 2 of 7 ATTACI: MENT 1 O
Trojan Nuclear Plant Supplemental Information on NUREC-0737 TMI Action Items 1.
Item II.B.3 - Post-Accident Sampling System Conceptual design of the improved Post-Accident Sampling System is complete. Comsip Delphi Company was selected as a vendor for major equipment supply, and the procurement contract was signed on February 6,1981 with equipment delivery required by August 1981.
The August 1981 delivery schedule was established to complete neces-sary modifications by January 1,1982.
In spite of our efforts to assist the vendor, we have not yet received any equipment at Trojan.
In July, Comsip Delphi Company slipped the shipment schedule date-to October 26, 1981 and recently informed us that the equipment would not be shipped untilkJanuary 16, 1982.i We estimate approximately 12 weeks to install, test and qualify the system as operational. Due to this delay and continued uncertainty of vendor performance, this Action Item will not be completed by January 1,1982 as requested in NUREG-0737.
We anticipate that the Post-Accident Sampling System will be operational before August 1, 1482.
It is expected that implementation of the necessary modifications can be completed I
without Plant shutdown.
In the interim, PCE will maintain the post-accident smopling proce-M-
dure outlined in Item 2.1.8.a of PGE's submittal of April 15, 1980 (Page 14 of the Attachment) to the NRC.
This interim procedure was reviewed and approved by the NRC letter of April 23, 1980 trans-mitting a safety evaluation of the TMI Short-Term Actions.
2.
Item II.F.1.1 - High-Range Effluent Radiation Monitors The original design concept for main steam line monitoring investi-gated in 1980 was to utilize a system which extracted a small bleed-off flow of steam. This sample was to be reduced in pressure and temperature to allow monitoring through a thin valled. pipe.
The advantage of this design concept over adjacent to main steam line monitors was the potential for significantly lower levels of detecta-bility for Xenon 133.
However, during the design evaluation in early 1981, this approach was determined to be unacceptable due to unavaila-bility of ' proven vendor designs for bleed-off steam monitoring systems and technical dif ficulties with installation of an acceptable tap-in point which would assure representative steam line sampling.
Selection of the vendor proposal for the adjacent-to-line monitors was completed and the purchase order was issued on October 15, 1981 for detectors and associated equipment. The equipment delivery schedule quoted by the vendor is approximately 6 months.
Expected
. installation time for the monitors is approxinately 12 weeks and no' Plant shutdown will be required for a. completion of the installation.
Based on these schedules,'it is expected that the main steam line
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monitors will be operational before August 1, 1982. The delay is attributed mainly to the prolonged design review required for the r
-a Trojan Nuclear Plant D. G. Eisenhut Dockat 50-344 April 28,1982.
License NPF-1 fage 3 of 7
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appropriate monitoring method (ie, off-line monitors versus adjacent-to-line monitors) and evaluation of vendor proposals.
In addition to unavailability of proven design for off-line monitors for main steam lines, which necessitated an extensive amount of design and engineer-ing review before it was cancelled, another factor for the prolonged design review was due to an ambiguous NRC requirement for the secon-dary side radiation monitoring which is described differently in all three documents:
NUREC-0737, NUREG-0651 and Regulatory Guide 1.97.
The adjacent-to-line monitors will be located below each main steam-line upstream of and in close proximity to the main steam PORVs and code safety valve header. The measurement range of the detector will be from 1 x 10-1 uCi/cc to 1 x 103 uCi/cc (equiva-lent Xenon 133) in accordance with Regulatory Guide 1.97 (Rev. 2).
In the interim, PGE will maintain the grab sampling and analysis procedure described under Item 2.1.8.b of PGE's letter to the NRC dated April 15, 1980, which is in effect at Trojan based on the NRC letter of April 23, 1980.
Status of the implementation date for the noble gas high-range radiation monitors for Containment purge (PRM-1), condenser air jet ejector discharge (PRM-6), and Auxiliary Building discharge (PRM-2) is discussed in-Section 3 (Item II.F.1.2) below.
3.
Item II.F.1.2 - Effluent Iodine and Particulate Monitoring System
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t Skid-mounted' process radiation monitors designed by Victoreen will be installed to monitor or sample / analyze iodine and particulates in the ef fluents. Normal-range iodine and particulates will be monitored by on-line detectors, while accident-range activity will be sampled for laboratory analysis.
Conceptual' design of the system is complete, and the purchase order for necessary equipment was issued on September 24, 1981. Estimated lead time for equipment delivery is approximately 7-8 months based on the vendor's quoted schedule.
Considering the required installation time of 8 weeks, this Action item will not be completed until August 1, 1982.
It is expected that Plant shutdown will not be.necessary for completion of this action.
This schedular delay was attributed to longer-than-anticipated lead time in review of design and vendor proposals, and the development of an integrated system approach for iodine / particulate monitoring and high-range noble gas monitoring (Action Item II.F.1.1).
The skid-mounted radiation monitors will replace the existing radia-tion monitors for Containment purge (PRM-1), condenser air jet ejector discharge (PRM-6), and Auxiliary Building discharge (PRM-2). The integrated system by Victoreen consists of.two skids; one for normal-range noble gas and iodine / particulate monitoring, and one.for high-range iodine / particulate grab sampling-and noble gas monitoring.-
The high-range noble gas channels for PRMs-1 and -6 were ordered in T
September 1980 from the same manufacturer, Victoreer, and were
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- Trojan Nuclear Plant D. G. Eisenhut Docket 50-344 April 28, 1982 i
License NPF-1 Page 4 of 7
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- monitors' are integrated into the high-range skid at the factory.
scheduled for installation by January 1,1982.
Due to the integrated system approach, Victoreen was advised to hold the shipment until the The integrated system approach was chosen because of limited space i
availability as well as for providing improved reliablity in sampling for an accident condition. Due to increased time required to develop an integrated approach, the buplementation schedule of this portion of Action Item II.F.1.1 for the effluent noble gas radiation monitors needs to be revised to August 1, 1982.
J Until the completion of the Victorcen monitoring system, PGE will maintain the grab sample procedure described in Page 29 (Item 2.1.8.b, Section B) of PGE's letter to the NRC dated January 2,1980.
This i
procedure was reviewed and approved by the NRC letter of April 23, 1080 for interim use at Trojan.
1 Additionally, the NRC clarification letter of October 31, 1980 sug-7 gested the use of isokinetic sampling in accordance with Appendix C to ANSI 13.1-1969.
The following is additional information regarding isokinetic sampling of effluents:
All Trojan effluent monitors draw samples through iso-kinetic nozzles designed for normal flow conditions. The isokinetic nozzles maintain the sample flow at a constant rate which is fixed for the normal effluent flow condition of each discharge line. The sampling rate remains unchanged for post-accident conditions.
Providing isokinetic sampling r
i for normal flow conditions assures that as the ventilation flow rate decreases for post-accident conditions, the sample velocity will be higher and provide a conservative estimate of effluent particulates.
Since PRMs-1 and -2 both sample downstrean of HEPA filters, the maximum particle size in the effluent stream is less than.3 microns.
The discharge stream from the steam jet air ejector will contain particulate with diameters less than 5 microns due to. the condenser which acts like a high-efficiency scrubber. ANSI 13.1-1969 states that i
the fractional error is insignificant for sampling when the i
particulate diameter is less than 5 microns..Therefore, the present sampling configuration with isokinetic nozzles will t
provide a suf ficient representative sample during both normal and accident conditions.
PGE therefore intends to comply with the provision of isokinetic sampling in accordance with Appendix'C to ANSI 13.1-1969, which is listed in NUREG-0737 as an acceptable alternative.
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4.
Ac tion Item II.F.1.6 - Containment Post-Accident Hydrogen Monitoring PCE's letter of May 4,1981 provided the NRC with f the results of l
preliminary design review of the existing Containment Hydrogen Monitoring System. A description of design modifications to prevent i
the' moisture condensation in sample lines from ' adversely affecting sampling and to install an additional solenoid valve on the sample 6
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a Trojan Nuclear Plant D. G. Eisenhut Docket 50-344 April 28,1982-License NPF-1 Page 5 of 7 return line was discussed in the letter. A subsequent detailed review ~of the existing monitoring system concluded that the existing sc monitors should be replaced with environmentally qualified monitors manufactured by Teledyne Analytical Instruments in order to comply with the design criteria for environmental qualification in NUREG-0737.
The purchase order for the Teledyne units was issued on September 14, 1981. The' estimated schedule for equipment delivery is approximately 14 weeks, with shipment now projected for the middle of December 1981.
It is expected that no Plant shutdown is required for a completion of the modifications. Due to the required time of 10 weeks for installa-tion of the system, it is now anticipated that the Containment Hydrogen Monitoring Syste= will be completed before August 1, 1982.
In the interim period until completion of the qualified monitoring system,-the existing monitoring system will be available for operation to provide an acceptable level of reliability for Containment hydrogen analyses as discussed in the PCE letter of May 4, 1981-to the NRC.
I The Teledyne monitoring system will not require use of sample lines traversing occupied areas.
Therefore, the previously identified relocatian of the hydrogen monitoring panel in response to Action item II.B.2, Plant Shielding Review, is no longer necessary.
5.
Action Item II.F.2 - Instrumentation for Detection of Inadequate Core Cooling Installation of major components for the Reactor Vessel Level Indi-cation System (RVLIS) designed by Westinghouse for detection of i
inadequate core cooling will be completed by January 1, 1982.
However, as discussed in the PCE letter of July 17, 1981, the RVLIS will not be made operational until after the refueling outage in 1982, since certain electrical terminations need to be completed and necessary preoperational test, functional tests and system calibration / filling have to be conducted. PGE does not intend to operate the RVLIS until the semi-scale facility test results are reviewed and found acceptable for RVLIS operation by PGE.
This is consistent with the NRC requirement of post-implementation review for the RVLIS operation in NUREG-0737.
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Trojan Nuclear Plant D. G. Eisenhut Docket 50-344 April 28, 1982
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Licensa NPF-1 Page 6 of 7 ATTACHMENT 2 O
4[y Trojan Nuclear Plant Updated Status of the TMI Action Items II.D.l.2, II.K.3.1 and II.K.3.5
- 1.
Item II.D.l.2 a Performance Testing of PORVs and Safety Valves Subsequent to the meeting on July 17, 1981 between the NRC and representatives of the PVR utilities for the EPRI PWR Safety and Relief Valve Test Program, a letter was submitted to the NRC on July 24, 1981 by R. C. Youngdahl (Consumers Power) summarizing status of the ongoing and expected schedules for its completion. On October 2, 1981 another meeting was held between NRC and EPRI PUR utilities to provide updated status report of the test program and to discuss a possible _chedule change.
PCE, a sponsor of the EPRI Valve Test Program, will continue following the progress of the EPRI Program and intend to complete the Action Item II.D.l.2 in accordance with the scope and schedule acceptable to the NRC and PWR utilities group.
2.
Item II.K.3.1 and 2 - PORY Isolation System Westinghouse Owners' Group submitted by letter OG-52 dated March 13, 1981 to J. R. Fuller, Special Projects Branch of the NRC, WCAP-9804 "Probabilistic Analysis and Operational Data in Response to
- Gj It em II.K.3.2 f or Westinghouse NSSS Plants".
That submittal identi-n>
fied the probability of a stuck-open PORV LOCA as low, particularly in light of post-TMI modifications.
The report provided operational data confirming the probabilistic data.
It was demonstrated in WCAP-9600 that Westinghouse plants can sustain a PORV LOCA without causing core damage.
Based on the low probability and acceptable consequences of a stuck-open PORV, particularly in light of post-TMI modifications, procedure changes and operator training, we conclude that an automatic PORV isolation system is not required.
3.
Item II.R.3.5 - Automatic Trip of Reactor Coolant Pump PCE's letter of July 17, 1081 and Vestinghouse Owners' Group letter 0C-60 dated June 15, 1981 indicated that further information on the small break model would be available in July 1981.
That material-has not been formally submitted to the NRC pending NRC acceptance of the information already submitted. When the NRC review is com-plete, Westinghouse Owners' Group intends to make a final submittal on the small break model. As stated in the letter OG-60, the Owners' Group will address, within at least 3 months after the NRC approval of the model, application of the approved model to the RCP. trip i
issue.
4.
Item III. A.2 - Improving Emergency Preparedness - Long Term The PGE letter of July 2,1981, provided our proposed method of
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calculating dispersion coefficants in the Emergency Planning Zone
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and offsite doses.
In addition, the letter committed PCE to I
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- D. - G. Eisenhut
' Docket 50-344 April 28, 1982 License NPF-1 Page 7 of 7 j
provide, by January -1,1982, our course of action regarding the
. items. of NUREC-0654, Appendix 2 concerning the meteorological measure-ments system in accordance with the proposed Revision 1 to Regulatory i
Guide 1.23 and-remote interrogation of meteorological measurements. As of the date of this' letter, we have not received-the results of the 4
i NRC staff review of-this submittal.
Due to the lack of finalized ' guidance from NRC on ' hese issues, PGE -
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t cannot at this time commit to the' January 1, 1982 submittal date.
PGE's resporse to these items will therefore be deferred until sufficient final NRC guidance is received, in particular:
1.
The final version of Revision 1 to Regulatory Guide 1.23.
2.
Final guidance on requirements for remote interrogation of meteorological data, including hardware and data transmission formats.
3.
Guidance concerning the meteorological elements to be i
considered in the development of an emergency plan and l
'in the application to the Class A model for varying i
terrain environments.
I Once sufficient guidance is received, PCE will provide a schedule for a submittal on these issues.
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