ML20086S069
| ML20086S069 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/27/1984 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097, TASK-1.C.1, TASK-1.D.1, TASK-1.D.2, TASK-1.E.1, TASK-2.B.1, TASK-2.B.2, TASK-2.F.2, TASK-3.D.3.4, TASK-TM 5211-84-2045, NUDOCS 8403010347 | |
| Download: ML20086S069 (21) | |
Text
'
GPU Nuclear Corporation a Nuclear
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Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer"s Direct Dial Number:
February 27, 1984 5211-84-2045 Office cf Nuclear Reactor Regulation Attn:
D. G. Eisenhut Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Sir:
Three Mile Island Nuclear Static.), Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 NUREG 0737 Selective Item Status On January 30 and 31, 1984, members of our Staffs met to discuss the status of long term NUREG 0737 items. At the conclusion of those meetings and in your letter dated Feb. 22, 1984 you requested that GPUN formally provide status and justification for 9 NUREG 0737 iterrs:
I.C.1 Emergency Operating Procedures I.D.1 Control Room Design Review I.D.2 Safety Parameter Display System I.E.1.1 Emergency Feedwater Long Term Upgrade II.B.1 High Point Vents II.B.2 Plant Shielding Design Review II.F.2 Inadequate Core Cooling 1I1.D.3.4 Control Room Habitability Suppl.
Reg. Guide 1.97, Rev. 2 8403010347 840227 PDR ADOCK 05000289 F
PDR GPU Nuclear Corporation is a subsidiary of the General Public Utikties Corporation g
D. G. Eisenhut 5211-84-2045 Attached please find the information that you requested. This letter is also responsive to your letter of December 22, 1983 concerning the restart status meeting of December 16, 1983 as indicated by the items marked with an asterisk
(*).
Finally you should note that the schedules provided are ambitjous but are achievable. We will keep you informed of any developments that result in major schedule changes.
Sincerely,
/
ukill Vice President - TMI-1 Swom & Subscribed to Before me this h day of "*- - 3__p 1984.
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DARiA JEAN BE ARY. N01 arf PUFliC etttwN 80Ro. cAuPms county cc: R. Conte
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J. Van VlietRemtm, Pennsylvama Assoc'ation of Metana
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"NUREG t0737 (Iten I.D.2) - Safety Parameter Display System - SPOS 4
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(INTRODUCTION-
. Basic SPDS~
W
-The basic'lSPDS_is that portion of the final SPDS triat uses a subset of
'f cthe approximately-2500 points currently ~available in the computer data l base.' xThe ' basic' SPDS will' satisfy the major requirements of four of the five Critical; Safety Functione (CSF?s) including:
1'(i)1 Reactivity control'
~
"(ii): Reactor core cooling and primary. system heat removal (iii) Reactor coolant system integrity -
^
(iv) ContainmentLconditions..
GhtNcurrentlymonitorsthefifthCSF,radioactivitycontrol,through:
c
- icontrol room equipment;and. procedures that can quickly status the radio-Jactivity of the entire plant. GPUN'will incorporate this CSF as part of x
the final-SPDS as-described below.
.A portion:of-the basic'LSPDS'has already been implemented at TMI-l in the form ofla post trip pressure-temperature plot. Trained personnel use this plot to' evaluate' core cooling and heat. removal from the-reactor coolant
.systs following a reactor trip. - This display supports the use of symptom -
oriented emergency. procedures; developed from the ATOG program. -Operators and Shift Technical Adviscrs are taught how to' interpret this display by a x
computer aided l instruction' course.
,. o, Final SPDS-I eThe ' final' SPDS will-include the ' basic' SPDS plus additionM.-parameters
=that are available in.the control' room but not on the: Plant Process 4 Computer System, such'as those parameters covering radioactivity control.
~
cThe-final.SPDS will also include parameters from the Raactor Coolant Inventory 1 Trending System.(RITS). These include the' hot leg and reactor J
- vesse1%ater level trending instrumentation.
- The current list of defined parameters -for both the " basic" and upgrades to
^ s the SPDS, constitute.the.TMI-l final'. SPDS. -As'the safety analysis, user k,
- guidelines,?CRT. display' development and operational experience continue,
~
'the-system may need: additional refinements. These~ enhancements to the
" final";SPDS will proceed on separate and independent schedules from those Jin this:33DS discussion.
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HISTORY In'its responses to Generic Letter 82-33, G3UN originally committed to have a basic 3PDS operational prior to Cycle 6 and the upgrades to the ' basic' SPDS by Cycle 7.
Current calendar estimates for those milestones would occur on or about July 1985 for Cycle 6 and December 1986 for Cycle 7.
Since then, GPUN has committed to have the TMI-l ' basic' SPDS available by January 1, 1985.
In a letter dated February 1,1984, GPUN also committed to upgrade the ' basic' SPDS by June 1985, or the first outage after this date, of sufficient length to allow the new instrumentation to be connected to the Plant Process Computer System.
In any case, the final SPDS will be operable prior to Cycle 6.
However, GPUN has initiated detailed planning and scheduling in an attempt to implement the final form concurrent with the
' basic' SPDS. See the discussion in the ' Hardware Implementation' section that' follows.
The SPDS has evolved as a result of work done to define the objectives of the SPDS and the parameters required to meet these objectives. GPUN furnished the NRC on February 1,1984 a complete list of the SPDS critical safety functions and the parameters associated with each function.
III.
STATUS AND SCHEDULE JUSTIFICATION The following is a brief description of those major milestones in the SPDS implementation schedule that require significant decisions. The outcome of the work conducted to reach these milestones plays a significant part in the subsequent work segments to accomplish SPDS implementation. In order to maintain the necessary controls to accomplish its goals, GPUN has committed the appropriate resources (manpower and time) to complete these work items in an orderly fashion.
Thus, the following work segments require substantial completion prior to starting the next item, GPUN will initiate parallel efforts where practical to expedite implementation.
o SPDS Safety Analysis i
GPUN is currently performing an SPDS safety analysis that identifies those Critical Safety Functions (CSFs) that describe the safety status of the plant.
The selection process has also identified additional instrumenta-tion / parameters that require inclusion into the existing plant computer
-data base.
As part of the Verification / Validation (V/V) effort, GPUN is developing transient / accident scenarios to use in testing the adequacy of the SPDS parauf.ter selection. Upon completion of the internal review and comment resolution of the parameter selection, GPUN will submit the safety analysis to the NRC'(by April 30, 1984).
This por* ion of the SPDS program will require approximately 2 months to complete.
o User Guidelines GPUN has developed preliminary user guidelines in the form of flow cnarts for each CSF.
These flow charts are also used in the parameter selection
,]rocess. Once the safety analysis parameter selection is complete, GPUN will define a set of alarms for aach CSF for both power operation and transient / accident conditions. These alarms will be assigned priorities and incorporated into the existing plant computer alarm processor.
Finally, _ G3UN will update the user guidelines and convert them into both a flow chart and written format in order to develop not only the CRT displays but_ also the training program as well.
This portion of the SPDS program will requjre approximately 3 aanths tc complete.
o Displays Developed GPUN will develop the CRT displays to provide concise and unambiguous information to the user so that trained personnel will have access to these displays via the CRTs presently available in the control room. The display development will employ the safety analysis and the user guidelines to group the parameters into display information categcries. The comments and i
suggestions from a preliminary review will produce draft CRT displays subject to final review by Plant Operations, Plant Engineering and Human Factors Engineers. Potential users will perform walkthroughs of the draft displays to determine the displays' final form. Upon completion of the walkthroughs, GPUN will release the final CRT display design for implemen-
.tation.
This portion of the SPDS program will require approximately 2 months t2
- complete, o Users Tra!ned The SPDS esers will receive proper training on the SPDS philosophy, design and use.
J. PUN will develop lesson plans using the safety analysis and user guidelines as well at the transient / accident scenarios to show the users how the SPDS will function. The training itself will span 6 weeks to cover all shifts during the rormal operator training cycle.
The lesson plan and transient / accident scenario development portion will require approximately 2 months to complete. The actual training will be performed' aver a normal 6 week operator _ training cycle, o Hardware Implementation GPUN finalized on 2/1/G4 the project scope for connecting thc additional parameters to the Plant Process Computer. By 3/1/84, GPUN will award the contract ~for engineering. Since the duration for a standard project of comparable scope would result in engineering release for construction in
[
I
'11/84, GPUN is currently expediting the design engineering and review process. As a result,-the engineering release.for construction will occur-
'in 7/84.
The engineering design process consists of the following:
.o.
. Systems De' sign Descriptions (criteria and_ final description)-
4
'o= ~PreJiminary Engineering Design Review o
Safety Evaluation
-'o
. Material Purchase Requisitions
.o Fire Hazards Analysis o. Detailed Drawings (aoprox. 150 drawings) o-Installetion Specification
-o-Operability, Maintainability, Constructability Review The majority-of the construction is in the Control Room and cannot proceed-
- when the plant-is operating. The release of engineering in 7/84 will
~
support completion of construction tr/1/1/85 assuming plant availability.-
-If not, GPUN will. complete implementation of the ' final' SPDS during the
_first outage of sufficient-length prior.to Cycle 6.
- IV.~
BIBLIOGRAPHY F
. GPUN:
-August 4,'1983 Gilinsky. Response
-November 28, 1983 Gilinsky' Response Update April 15, 1983 -Response to GL 82 4 February 1, 1984 SPDS Status
. NRC NUREG 0737 I.D.2 NUREG 0737-Supplement 1 (GL 82-33) 12/17/82 NUREG 0696- ~
4 g
NUREG 0737 -(Item I.E.1.1) Emergency Feedwater Long Term Upgrade I.
INTRODUCTION in accordance with the requirements in NUREG-0578 and 0737, the commitments outlined in.the TMI-1 Restart Report, the seismic concerns identified in Generic Letter #81-14, and the supplemental requirements addressed in the Atomic Safety and Licensing Board Partial Initial Decision, GPUN will upgrade tne Emergency Feedwater System to a safety grade system. The modifications implemented as part of this upgrade include mechanical system configuration changes, mechanical and electrical equipment qualifications (seismic and environmental), changes to the initiation and control system for EFW com-ponents, and seismic upgrade of piping sections in the Main Steam and Emergency Feedwater systems.
II.-
HISTORY The EFW System upgrade to safety grade included a review of Intermediate Building flooding, overfilling and overcooling of the OTSG's, pipe whip, seismic, water inventory, environmental qualification and single failure proof. As a result of this review, GPUN identified the following modifica-tions to be completed in the long term.
-(l)
Safety grade EFW control and block valves.
(2).
Upgrade SFW pump recir;-line from control valves EFV-8 to condensate storage tank to seismic.
(3)
Modify the vent stacks for MSV-22 and MSV-4 to seismic.
(4)
Expand flooding capacity in the event of a MFWLB by removing some walls in the alligator pit and tendon access gallery.
(5)
Provide.eafety grade power to COV-llis and upgrade-cable-routing to COV-14 to seismic.
-(6)
Provide safety grade EFW initiation and MFW isolation on high main steam /feedwater differential pressure.
(7)
Provide safety grade OTSG level instrumentation and signals for MFW OTSG high level isolation and low level initiation of EFW.
(8)
Provide dual setpoints for OTSG level control using EFV-30's.
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Provide safety grade automatic ~ control of EFW independent of ICS.
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Provide safety grade MSLRD system for WW system.
(11)-
, Provide'overspeed tripLin the control room for the turbine driven
~
.EFW pump.
~
(12)
Provide a. safety grade flood protection alarm in the alligator pit.
(13)-
Upgrade.the water level indicat' ion and low-low water level alarm in the control room for-each condensate storage tank to ssfety grade.
III. -STATUS AND SCHEDULE-JUSTIFICATION' a.
GPUN has awarded all architectural engineer service contracts for the EFW long Lterm modifications (except for cable and conduit which is on an expedited schedule). 3)UN is accelerating modification (2) above for_ targeted comple-
- tion'~in June 1984. 'The remaining long teIn items will have basic engineering
- packages released.tu:the. field in mid July J.984.
The remaining major com-ponent.for procurementcis'an electranic cabinet'for item (1) to be delivered in._ Septemoer:1964.. GPUN wf.11 complete all modifications prior to Cycle 6.
However,ilf TMI-l remains in the current shutdown mode,. GPUN will complete all modifications in the 4th quarter of 1984.- (Note: GPUN. learned on Feb. 17,-
1984 from the valve manufacturer that 2 of the ordered valves had defective
- forgings. GPU is attempting to resolve the problem in order to maintain current schedule commitments.)'
' IV.
BIBLIOGRAPHY GPUN"
~ Restart Report Section 2.1.2.6 Augus.t 23, 1983 (83-232). Long Term EFW Mods NRC:
i
-NUREG 0737 II.E.1-'1&2 NUREG 0680 PID 12/14/81 e.
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NUREG 0737 (Item II.B.1) High Point Vents I.
-INTRODUCTION In response to NUREG 0737 Item II.B.1 and 10CFR50.44, GPUN has installed high point vents in the hot legs, and pressurizer.
GPUN will install the reactor vessel head vent in the first quarter of 1984. The design of these vents allows the release of non condensible gas from the reactor coolant system following an inadequate core cooling event. These valves are remotely operated from the control room and have instrumentation to indicate flow /no flow.
II.
HISTORY Following the accident at TMI-2, the NRC in NUREG 0660 and later in NUREG 073/, recognized the need for remotely operated high point "ents.
In response to these. requirements GPUN developed an RCS ventinc system oescribed in the TMI-1 Restart Report. Leter the NRC issued 10CFR50.44 requiring installation of these vents.
III.
STATUS AND JUSTIFICATION GPUN has. installed the pressurizer vent and hot leg vents. Tbs engineering is complete for the head vent and the RCS pressure boundary for the head vent has been modified..GPUN will complete the remaining electrical and piping por-tions in the first quarter of 1984. ATOG procedure covering operation of the vents under accident conditions has been issued and GPUN will complete the training on these procedures by the end of February 1984.
IV.
BIBLIOGRAPHY-GPUN Restart-Report Section 2.1.2.2 September 3, 1981 (Lll 239)
August 23, 1982 (82-180)-
NRC NURIG 0737 II.B.1 NUREG 0680 Add Item 4 10CFR50.44 March 16,1982 October 17, 1983 t-
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NUREG 0737 (Item II.B.2) Plant Shielding Design Review I.
INTRODUCTION In accordance with the requirements of NUREG 0578 and 0737, GPUN conducted a Plant Shielding Design Review (PSDR). The purpose of the PSDR was to deter-mine if post acc1Jent radiation fields limit personnel access to vital areas necessary for recovery operations or whether the radiation fields degrade safety related equipment. The design review concluded that modifications were laquired to a.
control post-LOCA baron precipitation b.
allow operation of MCC 1A & B (a wall has been added and this modification is complete).
The present project scope includes the installation of:
(1) A new post-accident baron precipitation control byr-ass line and valve in the Decay Heat Removal System (DERS).
(2) A reach rod extension on the new bypass valve (3) Relocation of an existing reach rod extension on the DHRS.
II.
HISTORY TMI-l Restart Report, Amendment #25 (5/13/81) identified the original project scope that included the installation of remote valve operators on the DHRS as i
well as the relocation of an existing reach rod extension. During the last half of 1981, GPUN experienced several procurement difficulties related to improper proposals from vendors. 'In January 1982, GPUN management, due to the OTSG repairs, placed the engineering and design effort of the PSDR on hold.
When.the project was reactivated in May 1982, GPUN experienced continued
- procurement' problems throughout the remainder of the year.
Thus, in order to circumvent the continued procurement _ difficulties, GPUN reexamined the ori-ginal design and proposed.an alternate project scope. By mid 1983, GPUN decided on an acceptable alternate and notified the NRC in October 1983. By the end of 1983, GPUN awarded the A/E design contract and completed the evaluation offvalve vendor proposals.
III.
STATUS AND SCHEDULE JUSTIFICATION
-The. final milestones:
o Resolution of various exceptions contained in the valve vendor proposals.
y-
. o Award of DHRS bypass valve order by the end of February ISG4.
o " Release for Construction" installation package by mid-April 1984.
-o Delivery of bypass. valve in August, 1984.
O Completion of installation and modifications in the fourth quarter of 1984
-subject to plant availability.
IV.
BIBLIOGRAPHY GPUN Restart Report Section 2.1.2.3 January 23,'1981 (TLL 680) Resp. to NUREG 0737 June 15, 1982 Response to Generie Letter 82-05
.May 21, 1982 Reseponse to Generic Letter 82-05 September 20, 1982-(82-221) Schedule October 21, 1983-(83-280). Alternate Solution
.NRQ NUREG 0737 II.B.2 NUREG 0680 2.1.6.b
~ January 1, 1983 SECY 82-384/A A
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s NUREG 0737 (Item II.F.2) Instrumentation for Detection of Inadequate Core Cooling I.
. INTRODUCTION NUREG 0737 requires the' installation of instrumentation for the unambiguous
- detet. tion.of Inadequate Core Cooling (ICC). Therefore, in accordance with these MJREG 0737 requirements, GPUN has or will install' the following new instrumentation:
o Saturation Margin Monitors GPUN has installed redundant. saturation ir.argin monitors using qualified safety grade' signal conditioning equipment and existing control grade input signals.- The system, as installed, satisfies the functional intent of NUREG 0737.o As a further enhancement of the existing system, GPUN will provide safety grade temperature input signals as well as replace the present digital indicators with seismically qualified units.
or Incore Thermocouples-
. At TMI-1, all 52 incore thermocouples are comected to the plant computer.
'as the primary display system. However, GPUN has ir. stalled and connected sixteen thermocouples (four from each quadrant) to a safety grade backup Ldisplay! system (BIRO). Except'for the commercial grade. digital indicator, the design and installation conforms'to the requirements of NUREG 0737
.(Item II.F.2). GPUN will replace the present digital indicator with.a
. seismically qualified unit following testing.
o Reactor Coolant Inventory. Trending System (RITS)
The RCITS will allow the control room operator to trend Reactor Coolant l'
System (RCS)~ inventory under static.and dynamic conditions.
The operator.
. can monitor water level in the Reactor Vessel (RV) and hot-legs.when the RC
~
Epumps are not running.- When the RC pumps are operating, the operator will
-be'.able tc trend void fraction,in the RCS.
To-measure water level, GPUN will connect differential pressure trans-mitters from the vent connections at the top of each hot leg and the RV.
. head to a common tap in the Decay Heat Drop Line (DHDL). The. design also provides for process instrumentation and signal conditioning. electronics to
. correct'for changes in~ water density.
+
-In order to monitor RCS void fraction, GPUN has developed a computer algorithm to convert RCP motor power data into RCS void fraction..The r
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RITS will display in the control room, via the plant computer, both the trending of void fraction and water inventory.
o Other Instrumentation Additional instrumentation G)UN has already installed that aids the opera-tor in determining ICC include:
Wide Range RC Pressure Pzr, Pressure and Le', 1 EFW Flow Wide Range T at h
Escondary Side Steam Pressure and OTSG Water Level II.
HISTORY After considerable studies and interaction between the NRC and B&W Owners Group, the NRC issued an order on December 10, 1982, directing the B&W Owners to install a Reactor Coolant Inventory Trending System. Following a submittal of a response to this order on March 10, 1983, GPUN continued to investigate the optimum location for the lower d/p tap and the method of compensation of the water level signal for changes in RCS fluid density. GPUN expedited the detailed design of the DHDL tap to permit installation prior to restart. The actual installation occurred in December 1983.
III.
STATUS AND SCHEDULE JUSTIFICATION o Saturation Margin Monitor GPUN has installed a qualified scfety grade temperature sensor in each RCS hot leg.
The addition of these input signals requires termination of the safety grade T at leads within the Foxboro signal conditioning cabinets.
h GPUN will accomplish this by June, 1984.
Since the existing digital indicators require replacement with seismically qualified units, G)UN will purchase new commercial grade Weston digital indicators. GPUN will then under its own funding, seismically test and qualify a sample of these new Weston indicators. GPUN has decided to
. proceed in this manner due to the absence of traceability between the meters installed several years ago and those purchased for testing.
Upon successful completion of the test program, GPUN plans to replace the currently installed meters at the first available outage of sufficient
- duration, o -Incore Thermocouples GPUN will replace the present commercial grade' digital indicator with a seismically qualified unit during the first available outage of sufficient duration. (See discussion above.)
+=
o Reactor Coolant Inventory Trending Systems In December 1983, P UN installed the Off)L d/p tap and developed the void
' fraction algorithm, GPUN has ordered all long lead items and expects this equipment onsite by Jme 1984. By the er.d of February 1984, the schedule calls for the t.ompletion of the engineering for a majority of the items inside the Reactor Building. P UN intends to finish the remaining engineering (primarily electrical) by the end of April with completion of the control room CRT displays by mid-May. The remaining scheduled items include GPUN submitting to the NRC in April, the operator guidelines for use of the displays and the submittal in July of the modified operating and ememency procedures. The entire modification is scheduled for completion
-in the 4th quarter of 1984 subject to plant available.
IV.
BIBLIOGRAPHY GPUN Restart Report Section 2.1.1.6 (Supp. 1 Pt lQ 39, 17)
August 17, 1981 (Lll 246) RV Water Level Septembe:- 14, 1981 (Lll 261) RV Water Level November 13, 1981 (L1L 324) RV Water Level March 10, 1983 (83-071) RV Water Level April 14, 1983 (83-116) RV Water Level
' August 25, 1983 (83-230) RV Water Level February 2, 1982 (62-607) Backup Incore T/C December 22, 1983 (83-369) Seismic Incore T/C June 115, 1983 (83-148) Subcooling Margin Monitor September 7, 1983 (83-250) 250 Subcooling Margin May 13,1983 (83-148) SM4 January 31, 1964 (84-20) Insdequate Core Cooling NRC NUREG 0737 II.F.2
^
NUREG 0680 2.1.3.b Order dated December 10, 1982 January 6,1982 Reject HLLIS as not complete June 14, 1983 Proc.eed with Design RITS PID - Technical Deceeber 14, 1981 SECY C1-582 and 82-407-ASL3 Hearings
NUREG 0737 (Item III.D.3.4) - Control Room Habitability I.
INTROOLCTION NUREG 0737 (Item III.D.3.4) requires provision of adequate protection for control room Operators against accidental release of Taxic and Radioactive gases. The installation of redundant isolation dampers and radiation / toxic gas detection systems within the Control Building Vantilation System (CBVS) can provide this protection.
II.
HISTORY Pickard, Lowe and Garrick, Inc. (PLG) completed a " Control Room Habitability Analysis Report" for GPUN on June 29, 1982.
This report identified no offsite and three onsite potentially hazardous gases, (carbon oloxide, ammonium hydroxide and cholrine gas) that could, after an accidental on site release, migrate to the Caltrol Room through the CBVS. Using Probabilistic Risk Assessment (PRA)-techniques, GPUN submitted a repcrt to the NRC on July 16, 1982, inferring that due to the low probability of occurrence, na detection systems for ammonium hydroxica and chlorine were required for the protectinn of Control Roon, operators. This submittal committed to providing low leakage isolation dampers in the CBVS actuated by high radiation signals. GPUN committed to complete the modification prior to Cycle 7.
On December 28, 1983, the NRC responded to GPUN's July 16, 1982 submittal, taking exception to GPUN's PRA dispositioning of ammmonium hydroxide and chlorine gas hazards.
The N3C required that GPUN provide design basis protection against these hazards.
III.
STATUS AND SCHEDULE JUSTIFICATION o GPUN intends to respond to NRC's inquiries on the Control Room Habitability System for TMI-l at the end of February, 1984.
o G3UN is planning to use the services of a contractor to reassess the ammonium hydroxide hazard through recalculations using a limited source dose of ammonium hydroxide. GPUN could limit the source dose by providing spill protection or by limiting the total quantity of ammonium hydroxide stored on site.
In order to eliminate chlorinc gas as a hazard, GPUN will evaluate the use of alternative blocides in place of chlorine gas for the water treatment system. Schedule and other considerations may dictate installation of a chlorine detection system as a more viable option. At the present time, GPUN is evaluating the need for leak tight dampers for radiation protection.
th, o In parallel ~ with the contractors evaluation, G3UN is funding an effort with an Architect / Engineer to provide an estimate and schedule for the engineering, design, and installation of isolation dampers and Toxic gas Detection System in the CBVS. GPUN will authorize the toxic gas detection systems at a later date if the contractors evaluation concludes that ammonium hydroxide and/or chlorine gas cannot be eliminated as hazards. An accelerated implementation schedule would be as follows:
o Determine Modification scope April 1984 o
Receivs NRC Concurrence June 1984 o
. Award contracts for detailed Engineering to an Architact Engineer July 1984 0-Complete Prelim. Eng. Design Review Oct.
1984 o
Order Long. Lead Items Dec.
1984 o
Delivery Long Lead. Items Aug.
1985 o
Issue Engineering package for installation July 1985 o'
. Complete Installation
- Dec.
1985 O
Complete.testin) and turnover to Plant
- Feb.
1986
- 0utagefrequiredwithscheduledependentonplcntavailability.
-GPUN will revise the above implementation plan depending on the results of PLG
-Inc. 's evaluation of toxic gas hazards.
IV.
. BIBLIOGRAPHY GPUN.
-October 23,.1981 (L1l 309)
November 9, 1981-(Lll 323)
March 4,1982 (82-051)
July 16,'1962-(82-1671
'NRC NUREG 0737 III.D.3.4
. December.28, 1983 i-i a
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NUREG 0737 - Supplement 1 - Reg. Guide 1.97 I.
INTRODUCTION Reg. Guide 1.97
" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant-and Environs Conditions During and Following an Accident" describes a method.for complying with the Commission's regulations to provide instrumentation to monitor plant variables and systems during and following an accident. The Reg. Guide prescribes a minimum set of variables to be measured as well as the design and qualification criteria for the instrumentation.
II.
HISTORY The B&W Owners Group established a Reg. Guide 1.97 Task Force to formulate and fully justify a generic position on Reg. Guide 1.97 for B&W NSSS plants.
In
' the course of its efforts to develop a generic position, the Tse< Force iden-tified a need for the evaluation of certain variables. The Task Force is currently preparing an evaluation and technical justification for selected Reg. Guide 1.97 variables that will:
a) Determine the significance of the variable to the monitoring and
- ranagement of design basis accidents for a B&W NSSS plant.
b) Define the qualilfication criteria considered necessary to support the accident mcaitoring function, c) Assess whether the typically supplied instrumentation is adequate for the required monitoring function.
III.
STATUS SCHEDULE JUSTIFICATION B&W is preparing data sheets for each variable providing the variable name, type, category, and range prescribed by the NRC in Regulatory Guide 1.97 compared to tbs recommendations based on the evaluation effort. Details will
-be provided in the data sheets to support each utility to determine its plant specific application of the generic recommendations. The data sheets will also provide details to help justify recommended deviation from or acceptance
' of the requirements in Regulatory Guide 1.97.
B&W will transmit the description of the evaluation process and completed data sheets for variables to the B&W Owners Group Regulatory Guide 1.97 Task Force as a draft report for review and comment in March 1984. B&W will then issue a final report for use by the Task Force in establishing a generic position on Regulatory Guide 1.97 in April 1984.
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GPUN.will submit to the E C a final Reg. Guide 1.97 report and implementation schedule no later than September 1984.
IV.'
BIBLIOGRAPHY GPUN l July 12, 1983 (5211-83-197) Rerposes to GL 82-33 April:15,1983 (5211-83-178) Responses to GL 82-33 NRC December 17, 1982 Generic Letter 82-33 Reg. Guide 1.97,' Rev. 2 3 f-
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NJREG 0737 (Item I.C.1) Emergency Operating Procedures (ATOG) i o
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-I..
INTRODUCTION-I As.part of the effort to improve operator response to. abnormal or emergency conditions, NUREG 0737 requires the improvement of emergency operating proce-
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dures (EOPs). TMI-l'has currently in place EOPs developed from the B&W Owners Group-generic procedure commonly known as ATOG (Abnormal Transient Operating Guidelinas).
The TNI-l E0Ps called Abnormal Transient Procedures (ATPs), pIovide the
. operator with guidelines that take a symptom oriented approach in dealing with emergency conditions'. These new !!TPs improved upon the old event oriented emergency procedures.;
t The TMI-l'ATPs provides the operator with a road map that guides him in-t
. dealing with the symptoms of a transient. Furthermore, the ATPs place the
. operator in a position to properly followup on specified actions. The opera-4 tor can move from procedure -to procedure without having to start from the beginning each time. The experienced operator now has a defined sequence he uses with. simplified rules comitted to memory.
II.
HISTORY
-In August 1980,.the B&W Owners provided a draft ATOG to the NRC. During.1981,
.@UN and B&W began. work on the TMI-l plant specific. ATOG procedures with some "nands.on" experience on the B&W simulvtor. By the end of 1982,-B&W resolved-
.. @UN comments and issued the final TMI-l ATOG in April 1983.
In an attempt to proceed quickly with the full implementation of ATOG, GPUN formed an ATOG l Implementation Committee.that met weekly.to assure the ATOG program would be in place.in the 1st quarter of~1984.
After verification of the ATPs'on the B&W simulator, GHA trained all the
-licensed operators in the classroom and replaced the old prochdures in'the icontrol-room with the new ATPs., Finally, the ATOG Implementation Committee.
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used the B&W simulator to develop the simulator. training program in preparation for the simulator training of.the operators.
- III.~ ' STATUS /PD SCHEDULE JUSTIFICATION 4.
o Training of.all the lice.nsed operator. crews will be complete by the end of
_ ;L March-1984.
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- 2 0. GPUN submitted'a Procedures Generation Package (PGP) to the EC at the end
-Tof January 1984. GPUN is now resolving-NRC questions on the PGP.
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IV..
BIBLIOGRAPHY (PUN
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June.30, 1981 (Lil 020)
March 31,1982 (B&W Owners)
June 15, lid 2 (B&W Owner 3)
March 14, 1983'
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December 29, 1983 January 26, 1984 NRC NUREG 0737 I C.l.
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NUREG 0737 (Item I.D.1) Control Room Design Review l
<I.
INTRODUCTION As part of the Control Room Design Review (CRDR), GPUN established a multl-disciplinary team and review program employing accepted human engineering practices.. The purpose of this review was to ensure that plant operators have the-proper environment with readable and understandable controls to safely operate the plant.
II.
HISTORY Prior-to the issue.of the requirement in NUREG 0737, GPUN conducted a review of the c6ntrol room design in 1980. - The review indicated a nunber of modifi-cations that were to be accomplished. All of these modifications are now complete. The NRC also reviewed the TMI-l control room design and documented its results in NUREG 0752 and supplement.
III.
STATUS AND CCHEDULE JUSTIFICATION.
GPUN has completed and submitted the final Control Room Design Report to NRC.
GPUN will complete by'Aprii 30, 1984, a -supplementary review of the control room using the emergency procedures based on ATOG to validate the control room task analysis. GPUN will then submit a supplementary report completing the
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requirements of Item I.D.1, by May 31,1984.
IV.
BIBLIOGRAPHY
_GPUN
'JJ1y 14,1980 (TLL 346) Control Room Engineering Review November 7, 1980 (TLL 559) Human Factors Engineering January 21, 1981 (Lll 019) Human Factors Engineering January 23, 1981 (TLL 680)-Response to NUREG 0737 January 16,_1984 Control Room Design Review NRC
- NUREG 0737 I.D.1 NUREG 0752 and Supplements Generic Letter 82-33 December 17, 1983 ASLB Hearings PID'
.-