ML19340D882
| ML19340D882 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, Zion  |
| Issue date: | 12/31/1980 |
| From: | Abel J COMMONWEALTH EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.C.1, TASK-2.B.1, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.3.1, TASK-2.E.4.2, TASK-2.F.1, TASK-2.F.2, TASK-2.G.1, TASK-2.K.3.02, TASK-2.K.3.03, TASK-2.K.3.04, TASK-2.K.3.12, TASK-2.K.3.13, TASK-2.K.3.15, TASK-2.K.3.17, TASK-2.K.3.21, TASK-2.K.3.22, TASK-2.K.3.27, TASK-2.K.3.44, TASK-2.K.3.45, TASK-3.B.2, TASK-TM NUDOCS 8101050500 | |
| Download: ML19340D882 (55) | |
Text
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O]j one rust National Plata. Chicago. tilinois Comm:nw:sith Edison O
Address Reply to: Post Off.cc Box 767 i
Chicago. tilinois C0690 De cember 31, 1980 f
j Mr. Darrell G. Eisenhut, Director 3
Division of Licensing M
i U.S. Nuclear Regulatory Commission Washington, DC 20555 N
Ek Un Subje ct :
Dresden Station Units 1, 2, and2lPS E
W
^
Quac Cities Station Units 1 and ?!
Zion Station Units 1 and 2 6
5 Responses to NUREG-0737 Items C
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~
Requiring January 1, 1981, Submittals NRC Docket Nos. 50-10/237/249, 50-254/265, and 50-295/304 j
References (a):
D.
G. Eisenhut letter to All Licensees dated October 31, 1980.
(b):
J. S. Abel letter to D.
G. Eisenhut dated De cember 15, 1980, i
Dear Mr. Eisenhut:
i Enclosed are Commonwealth Edison Company's responses to those NUREG-0737 items requiring January 1, 1981, submittals for Dresden, Quad Cities, and Zion Stations.
Please note that no response is provided for Dresden Unit 1, which is currently undergoing an extensive modification and de contamination outage.
The requirements of NUREG-0737 will be
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addressed prior to startup of the unit, now s cheduled for June, 1986.
One (1) signed original and seventy-nine (79) copics of t
I this transmittal are provided for your use.
t Very truly yours,
- /
l J.
. Abel i
Director of Nuclear i
Li censing j
cc:
Mr. James G. Keppler, Di re cto r i
Directorate of Inspection & Enforcement l
Region-III NRC RIII Inspector - Dresden RIII Inspector - Quad Cities l
RIII Inspe ctor - Zion 8101050 SC Q
[
ENCLOSURE Commonwealth Edison Company Responses to NUREG-0737 Items Requiring January 1, 1981, Submittals Dresden Units 2 and 3 Quad Cities Units 1 and 2 Zion Units 1 and 2 1.A.l.1 Shif t Technical Advisor - Trained per Lessons Learned (3);(4)
Category B; Descript ion of Long Term Program As dis cussed in the De cembe r 15, 1980, J.
S.
Abel letter to D.
G. Eisenhut, information con ce rning these items has already been submitted and more information will be provided by March 1, 1981.
I.C.1 Short Term Accident and Procedures Review 2.a, 3.a Inadequate core cooling; transients and accidents--
reanalyze and propose guidelines.
Dresden, Quad Cities Response As noted in Enclosure 3 of NUREG-0737 the analysis and guidelines required by this task have been submitted by the BWR Owners Group, and their a cceptability has been documented in D.
G.
Eisenhut's letter to S.
T.
Rogers dated October 21, 1980.
We therefore believe that no further action is required to comply with this requirement.
Zion Response The Westinghouse Owners Group has submitted, in a letter from B.
Jurgenson to S. Hanauer dated December 15, 1980, a detailed description of our program to comply with the requirements of Item I.C.1.
II.B.1 Rea ctor-Coolant-System Vents to NUREG-0737 lists a licensee submittal due January 1,
1981, for (3)
"p r o ce d u re s. "
This contradicts the July 1, 1981, date for Documentation Required contained in Enclosure 3 to NUREG-0737.
Dresden, Quad Cities, and Zion Station information will be submitted by July 1, 1981, as requested in the clari fi cation se ction.
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-2 11.8.2 Plant Shielding Dresden, Quad Cities, Zion Response We believe that the shielding studies completed January 1,
1980 (as required by NUREG 0578 Item 2.1.6.b) comply with the present NUREG-0737 requirements with the ex ception that in the Zion study the Chemical and Volume Control System (CVCS) was assumed to be isolated since it is automati cally isolated during an a ccident.
These studies are available for review.
All modifications as a result of these studies will be completeo by January 1, 1982, as required.
II.B.3 Post-Accident Sampling Dresden, Quad Cities, Zion Response We expect to comply with the NUREG-0737 requirements.
Therefore, no January 1, 1981 response is required.
II.B.4 Training for Mitigating Core Damage 1.
Develop training program.
A training program will be available for NRC review on January 1, 1981, as required.
II.E.1.2 Auxiliary Feedwater System Automati c Initiation and Flow I ndi ca t ion Dresd'en, Quaa Cities Response This item is not applicable to Dresden or Quad Cities Station.
Zion Response Our De cember 14, 1979 letter from D.
L.
Peoples to D.
G.
Eisenhut provided our justification that the existing automatic initiation and flow indication does not require modification.
This submittal provioed FSAR references and system drawings.
Therefore we believe that we have complied with the January 1, 1981 requirement that the li censee provide do cumentation to support the finding that the requirements of NUREG 0737 item II.E.1.2 are comp l e t e.
Te chni cal Spe ci fi cat ion changes are also there fore unne cessary for safety grade flow automat i c init i.at ion and safety grade flow i ndi ca t i on.
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. II.E.3.1 Eme rgen cy Power Supply for Pressurizer Heaters Dresden, Quad Cities Response This item is not applicable to Dresden at Quad Cities Stations.
Zion Response There has been no design criteria revision since the NRC, October 30, 1979 letter or the response contained in our letter from Cordell Reed to Darrell G.
Eisenhut dated October 18, 1979.
It is nur judgement that this response suf ficiently demonstrated that the Zion design was in a ccordance with the NRC position.
In our 45-day response to NUREG-0737 (J.
S.
Abel letter to D.
G.
Eisenhut dated December 15, 1980), we mistakingly indicated that documentation would be transmitted 'a the NRC as required.
NUREG-0737 requires further documentation f o r appli cants, not li cense e s.
Since this item is complete for operating reactors, no further response is required for Zion Station.
II.E.4.2 Containment Isolation Dependability Dresden, Quad Cities, Zion Response The containment isolation pressure for Dresden and Quad Cities Station is 2 psig.
Under normal operating conditions, fluctuations in atmospheric pressure and containment heat up c'a n result in pressure increases on the order of 1 psi.
Consequently, the present setpoint provides a very small margin above expected operating conditions and, therefore, no setpoint change is necessary.
This is especially true at the present time since the containments are being operated at approximately 1 psig until such time that the Mark I containment con ce rns can be resolved.
The current containment isolation pressure and safeguards actuation setpoint for Zion Station is 4.5 psig.
The Zion technical specification set a 1 psig limit on containment pressure during operation, and the containment pressure channel has a 1 1. 5 psig a ccura cy.
Therefore, the present setting only provides a 2 psi margin above the allowable channel fluctuation and no setpoint cnange is ne cessary.
_4 The above positions are consistent with the re commendations o f westinghouse and the General Electric Owners group.
The Owners grGups had de cided that each utility would respond independently.
Dresden, Quad Cities, and Zion Stations presently meet the requirements of position 6.
II.F.1 Accident Monitoring 1.
Nobel Gas Monitor Dresden, Quad Cities, Zion Response We do not expect to deviate from the NUREG-0737 position.
2.
Sampling and Analysis of Plant Effluents Dresden, Qoad Cities Response The changes to the previous requirements of this item are still under review to determine if any design changes are ne ce s sa r y.
Therefore final design details will not be available by January 1, 1981.
It is expected that this information will be available by the end of the first quarter of 1981.
It is expected that the January 1, 1982 implementation date will be met.
If we deviate from the NUREG-0737 position, we will supply the necessary information by April 1,
1981.
Zion Response We do not expect to deviate from the NUREG-0737 position.
3.
Containment High-Range Monitor Dresden, Quad Cities Response The containment high range radiation monitors at Dresden and Quad Cities Stations will be installed in drywell penetrations.
The penetrations have 0.688'- walk and 0.5" end caps which will have the ef fect of shielding the dete ctor f rom low energy gamma rays.
In NUREG-0737 the reason provided for the requirement that the monitor respond linearly to photons from 0.1 Mev to 3 Mev is to ensure accurate measurements independent of the energy
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spectrum of an accident.
We do not see this instrument as being particularly useful in quantifying the radiation release to the containment.
The instrument will be used as an additiunal indication to the reactor operators that a 1
degraded core situation exists or is developing f ollowing a loss of co o l a n t.
The a ctual quanti fi cat ion o r the radiation release to the containment will be done using the Post Accident Sampling system that is being installed under 1
item II.B. 3 o f NUREG-0737.
We feel that the loss in accuracy due to the placement of these detectors is outweighed by the increased availability that can be expe cted f rom detectors that are serviceable ouring normal operation.
Zion Response The system will be installed by January 1, 1982.
A ju s ti fi ca t ion for deviation from the NHC position will be provided by July 1,
1981 (as required) i f ne cessary.
II.F.2.
Instrumentation for Detection of Inadequate Core Cooling
?
Dresden, Quad Cities Response i
In our response to NUREG 0578 item 2.1.3b we referenced NEDO 24708 titled, " Additional Information Required for NRC Staff -
Generic Report on Boiling Water Reactors."
Se ction 2.3.2 of that report contains an analysis of level instrumentation for General Electric Boiling Water Reactors.
The conclusion of this report is that no additional instrumentation is necessary for the detection of inadequate core cooling.
Therefore no new instrumentation for the detection of inadequate core cooling is proposed.
Zion Response It is our intent that the design of this system shall be in a ccordance with the re cent NRC ' criteria.
An evaluation of the existing system design is being performed to determine compliance with NRC design criteria and identified Regulatory Guides.
Suf ficient time was not available to compile and submit the requested system documentation; this irefurmation will be submitted in the first quarter of 1981.
. II.G.1 Eme rge n cy Power for Pressurizer Equipment Dresden, Quad Cities Response This item is not appli cable to Dresden or Quad Cities Stations.
Zion Response There has been no design criteria revision since the NRC, October 30, 1979 letter or the tesponse in our letter from Cordell Reed to Darrell G. Eisenhut dated O ctobe r 18, 1979.
It is our judgement that this response suf ficiently demonstrated that the Zion design was in accordance with the NRC position.
In our 45-day response to NUREG-0737 (J.
S. Abel letter to D.
G.
Eisenhut dated December 15, 1980), we mistakingly indicated that documentation would be transmitted to the NRC as required.
NUREG-0737 requires further documentation for applicants, not li cen se e s.
Since this item is complete for operating reactors, no further response is required for Zion Station.
II.K.3.2 Report on Overall Safety Ef fe ct of Power-Operated Relie f Valve Isolation System Dresden, Quad Cities Response This item is not applicable to Dresden or Quad Cities Station.
Zion Response The Westinghouse Owners Group is in the process of developing a report (including historical valve failure rate data and documentation of actions taken since the TMI-2 event to decrease the probability of a stuck-open PORV) to address the NRC con ce rns o f item II. K.3.2.
However, due to the time-consuming processing of data gathering, breakdown, and evaluation, this report is scheduled for submittal to the NRC on March 1, 1981.
As required by the NRC, this report will be used to support a decision on the necessity of incorporating an automatic PORV isolation system as specified in task action item II.K.3.1.
. II.K.3.3 Reporting SV and RV Failures and Challenges Oresden Safety and relief valve f ailures to close will be promptly reported to the NRC.
Challenges to the safety and relief valves will be do cumented in the annual report.
Quad Cities This item has been reported over the past few years on the NRC Monthly Operations Report.
Failures have been reported as LEHs.
These pra ct i ces will continue to be performed.
Zion Failures or challenges to the primary system PORV's or safety valves will be promptly reported to the NRC.
Since there have been no failures or challenges of these valves as of April 1, 1980 ( cut of f date referred to in D.
G.
Eisenhut May 7,
- 1980, letter to all operating licensees), no report will be submitted.
II.K.3.12 Confirm Existence of Anticipatory Trip Upon Turbine Trip Dresden, Quad Cities Response This item is not applicable to Dresden or Quad Cities Station.
Zion Response The reactor protection system at Zion Station contains an anticipatory reactor trip on turbine trip.
This trip is de s cribed in FSAR Section 7.2.2 and is required by Te chnical Spe ci fi ca tion 3.1.
The re fo re, no modification is proposed or required.
II.K.3.13 HPCI & RCIC Initiation Levels l
l Dresden Response This item is not applicable to Dresden Units 2 & 3. since it does j
not have an RCIC system.
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Quad Cities Response The separation of the RCIC and HPCI initiation has been iound not to add significantly to plant safety.
This conclusion is based on an evaluation performed by General Electric on behalf of the BWR Owners Group, which was transmitted to the NRC by letter from R.H.
Bu chholz to D.G.
Eisenhut dated October 1, 1980.
The regt,lrement tha t t he RCIC logic be modified so that RCIC will restart on low water level will be implemented by July 1,
1981, provided that equipment availability does not be come limiting.
The modification being made tu Quad Cities Station will be described in a transmittal from the BWR Owners Group by January 1, 1981.
Zion Response This item is not applicable to Zion li.K.3.15 Isolation of HPCI and RCIC Dresden, Quad Cities Response The HPCI and RCIC pipe break detection circuitry will be nodified to preclude the possibility of spurious isolations caused by startup pressure spiking.
It is anticipated that this modification will be completed by July 1, 1981.
Since this is a post implementation review, the requested documentation information will be submitted by July 1, 1981.
Zion Response This item is not applicable to Zion Station.
II.K.3.17 ECCS System Outages Dresden, Quad Cities, Zion Response The required information is contained in Attachments 1, 2, and 3 to this enclosure.
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AI.K.3.21 Restart of CSS and LPCI Dresden, Quad Cities Response The BWR Cwners Group will submit an Owners Group position and review of this item by January 1, 1981.
The conclusion of this review is that change to the ECCS logic would not enhance plant safety.
The refore no modi fi cation is proposed for Dresden or Quad Cities Stations.
A cco rd ing l y, Te chni ca l Spe ci fi ca t ion changes are unne cessa ry.
Zion R onse This item is not applicable to Zion Station.
II.K. 3.22 RCIC Su ct ion Swit chove r Quad Cities Response Procedures calling for manual switchover to the suppression pool if the condensate storage tank level is low are presently in p la ce.
Dresden, Zion Response This item is not applicable to Dresden or Zion Station.
l II.K. 3.27 Common Re fe ren ce Level l
Dresden, Quad Cities Response i
The control room reactnr water level indicators at Dresden units 2 and 3 and Quad Cities units 1 and 2 have been rescaled such that all instruments now use the bottom of the separator skirt as a common zero.
This zero was chosen to eliminate the need for operatur retraining, and the numerous Technical Specification and procedure changes that would be required by the choice of any other zero reference.
Zion Response This item is not app l i cab le to Zion Station.
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. II.K.3.44 Evaluation of Transients with Single Failure Dresden, Quad Cities Response The BWR Owners Group will submit a report in response to this item by January 1, 1981.
Zica Response This item is not applicable to Zion Station.
II.K.3.45 Manual Depressurization Dresden, Quad Cities Response The UWR Owners Group will submit a report in response to this i
item by January 1, 1981.
Zion Response This item is not appli cable to Zion Station.
III.A.2 Emergency Prepa redness The submittal required by January 2, 1981, i s being transmitted under a separate cover let te r.
III.D.3.3 Inplant Radiation Monitoring (lodine)
Dresden, Zion, and Quad Cities Stations currently have the capability to sample and determine airborne iodine con centration using halogen cartridges.
Sample collection is by means of portable iodine samplers using iodine selective sample media (e.g., silver zeolite).
Analysis of samples is by means of portable single channel or multi-challen gamma analyzers.
As so cia ted training programs and procedures for determining l
airborne lodine con centration are in pla ce.
Several low-background, low-contamination areas at ea ch station have been identified through an engineering analysis of expected post-accident radiation fields.
Procedures will be modified to include identification of these areas so that samples and l
analytical equipment can be moved as necessary.
P ro cedu re modification will be completed by January 1, 1981.
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i r i III.D.3.4 Control Room Habitability Dresden, Quad Cities, Zion Response The hazard evaluation and plant modifications following the evaluation have been postponed one year, due to financial and engineering staff limitations.
The NRC was notified of this in a letter from C. Reed to 0.G.
Eisenhut dated July 25, 1980.
Our present plans are to submit the hazard evaluation by January 1, 1982, and to complete any necessary.nodifications by January 1, j
1984.
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DI'i'n d t'n Urt i ln : ) a r til 3 MQ; lvn t.<"o 0 0! v o - he u r i r l, July 22, 1974 System:
1.PC I L' nit 2 Valve MO-1501-19fi Valve would not oper a t e, invest inat ion 3,howed the valve operator vole to be separated from the va!ve boily.
Corrective action: reattached yoke to body.
Duration:
5 llours, 59 Minutes Au;;u s t 28, 1974 System:
Core Spray A pump riischarge at op-check valve 1402-8A tailed to rescat lollowiif, pump run.
The valve was manually closed to achieve proper at.
Duration:
2 llours, O Minutes November 14, 1974 System:
IIPC I Motor-operated valve MO-2-2301-6 would not operate.
Investination showcd motor terminal strips shorted due to a breaketown of the terminal board insulation. Corrective action; replaced terminal *, t r i p.
Duration: 4 9 IL"i r s, 20 M;:utes November 20, 1974 System:
llPCI DC motor for valve MO-2-2101-8 found to be overheatinn with evidence of commutator arcing due to dirt of commutator.
Correceive action:
rivit on was rebuilt.
Duration:
536 Ilours, o Minutes l
l November 27, 1914 System:
Core Spray Motor-operated valve MO-3-1402-24A would not operate looperly.
llu' baseplate for the 1imit switch contae! found cracked. Crack heIieved to originate from a previous water hanar. r in the line.
Correction action:
replaced baseplate.
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Duration:
22 llours, O Minutes l
December 21, 1974 System: Core Spray I
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Motor-operated valve MO-3-1402-4A would not close against syst em head.
Investipation showed the mot or t o he undersized f or t he application.
Corrective action:
mo li! ical ion m. ole 1o inst alI larger mot or (moditica-a lat er dat e).
tion completed at Duration:
2 llours, 25 Minutet.
e-
. January 12, 1975 System: Core Spray "B" pump discharge stop-check valve failed to rescat following pump surveillance run. Corrective action: valve manually stroked to achieve seat.
Duration:
0 llours, 55 Minutes January 20, 1975 System:
Emergency Diesel During surveillance testing, the engine started but tripped immediately on mechanical overspeed. The governor droop setting found to be im-proper. Corrective action:
reset governor.
Duration:
1 llour, 15 Minutes January 23, 1975 System: lipcl Motor-operated valve MO-2-2301-4 stopped mid-stroke. The movable con-t ts for the torque switch were found to be misaligned and dirty.
Cor-rective action: cleaned and realigned tocque switch.
Duration:
24 llours, O Minutes January 25, 1975 System: Core Spray "B" pump discharge stop check valve failed to rescat. Valve disassembled for inspection - no cause identified during inspection.
Duration:
2 Hours, 45 Minutes March 17, 1975 System:
Emergency Diesel Unit 2 diesel failed to start. Air start motor did not engage bull gear.
Corrective action:
replaced air start motor.
Duration: 44 Ilours, O Minutes May 20, 1975 System: ADS Electromatic relief valve 2-203-3C failed to open in response to manual signal. Pilot operating lever found out of adjustment. Corrective action:
properly adjusted lever.
Duratien:
140 Hours, 30 Minutes May 20, 1975 System: ADS Electromatic relief valve 2-203-3C failed to open in response to manual signal. Disassembly showed seal ring failed. Corrective action:
replaced seal ring.
Duration:
75 llours, 55 Minutes
. December 11, 1975 System: Emergency Diesel Unit 3 diesel would not respond to load changes.
Investigation showed a misalignment of the shutdown solenoid causing a loss of fuel flow control. Corrective action:
realigned solenoid and retightened lock nut found to be loose.
Duration:
28 Hours, 45 Minutes March 13, 1976 System: HPCI Valve M0-2-2301-4 was closed and failed to reopen.
Inspection showed dirty contacts in the supply breaker. Corrective action: breaker cleaned and inspected.
March 2'+, 1976 System: HPCI Duriag ISI inspection, HPCI safe-end fourd to be cracked; the unit was in refuel at the time.
Corrective action:
replaced safe-end.
Duration:
1198 Hours, O Minutes April 6, 1976 System:
Isolation Condenser Related to above item. Vessel safe-end found cracked and replaced.
May 10, 1976 System: Core Spray l
The breaker for motor operated valve MO-3-1402-25B tripped on thermal-l overload due to inadequate overload heaters. Corrective action:
re-placed heater with larger unit.
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Duration:
1 Hour, O Minutes l
May 25, 1976 System: ADS l
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Electromatic valve 2-203-3A failed to reclose following manual operation.
l Cause: excessive leakage on pilot stage. Corrective action:
replaced l
pilot.
Duration:
29 Hours, 57 Minutes j
l June 10, 1976 System: Core Spray Motor-operated valve MO-2-1402-4B would not close against system head.
l The valve stem was lubricated and torque switch setting checked.
Duration:
3 Hours, O Minutes l
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. June 25, 1976 System:
LPCI Tha breaker for pump 2C-1502 failed to close.
Inspection of breaker showed dirty contacts - cleaned same.
Duration:
1 Hour, 45 Minutes July 11, 1976 System: Core Spray Motor-operated valve M0-2-1402-24B was closed and would not reopen.
Investigation found a broken limit switch contact block - replaced same.
Duration:
2 Hours, O Minutes July 13, 1976 System: Emergency Diesel Diesel cooling water pump failed due to worn bearings - replaced pump.
Duration:
26 Hours, 30 Minutes September 30, 1976 System:
Emergency Diesel The 2/3 diesel generator showed output control problems.
Investigation showed a shorted scienium rectifier in field circuit - replaced same.
Duratioa:
30 Hours, O Minutes October 12, 1976 System:
LPCI Motor-operated valve MO-3-1501-27A failed to open.
Investigation found a loose terminal in the valve control circuit - tightened same.
Duration:
1 Hour, 30 Minutes October 29, 1976 System:
Emergency Diesel The Unit 2 engine failed to start. The plunger for the shutdown solenoid l
found out of adjustment - readjusted plunger to proper length.
Duration: 8 Hours, O Minutes November 13, 1976 System: HPCI
. Motor-operated valve 2-2301-8 would not operate. Valve stem found severed.
Replaced valve stem.
November 19, 1976 System: HPCI Identified logic wiring problem witt: valve MO-3-2301-8.
Valve would oscil-late then fail closed. Modification completed to correct problem.
I
. Duration: 2 Hours, O Minutes February 17, 1977 System:
LPCI Motor-operated valve MO-2-1501-32B was closed but would not reopen.
Investigation showed a limit switch adjustment problem. Corrective action:
readjusted limit switch.
Duratior.:
16 Hours, 20 Minutes March 22, 1977 System:
Emergency Diesel The Unit 2/3 diesel engine failed to start.
Investigation showed the failure to be due to a problem with the engagement of the air start motors. Corrective action:
replaced air start motors.
Duration: 6 Hours, O Minutes March 22, 1977 System:
Emergency Diesel Could not flash the field on the Ui.it 3 diesel generator.
Investigation located an intermittent short in a capacitor. Corrective action:
re-placed capacitor.
Duration:
10 Hours, 0 Minutes May 29, 1977 System: LPCI The LPCI/CCSW heat exchanger has tube leakage. Corrective action:
plugged leaking tubes.
Duration:
62 Hours, 45 Minuces June 3, 1977 System:
LPCI Motor-operated valve 2-1501-3A would not open when a pump in the loop was started.
Investigation showed a slightly bent stem attributed to an out-of-adjustment slide wire.
Corrective action:
readjusted slide wire and straightened stem.
Duration:
16 Hours, O Minutes June 11, 1977 System: ADS During unit startup, noted high pilot valve temperature on electromatic valve 3-203-3E.
The pilot valve was replaced.
Further investigation showed cause to be dirt under the seat causing seat leakage.
Duration: 4 Hours, O Minutes
. June 12, 1977 System: ADS Electromatic relief valve 3-203-3D had excessive pilot temperature.
In-vestigation found a defective stem in pilot stage.
Corrective action:
replaced pilot assembly.
Duration: 4 Ifours, O Minutes June 13, 1977 System: ADS The solenoid operating lever for electromatic relief valve 3-203-3C was sticking in the energized position.
Investigation showed a lubrication problem. Corrective action:
cleaned and lubricated operating 1cver.
Duration: 4 Hours, O Minutes July 12, 1977 System: Emergency Diesel The Unit 2/3 diesel engine tripped due to overspeed conditions while cperating under load. An investigation showed the generator frequency to have been improperly set.
Corrective action:
none.
Duration: 0 Hours, 35 Minutes September 10, 1977 System:
HPCI Following HPCI pump flow test, motor operated valve 2-2301-8 could not be reopened.
Investigation showed several possible causes:
- 1) water in limit switch housing, 2) water in torque switch housing, and 3) the valve stem had bent. Corrective action:
replaced stem and corrected switch problems.
Duration:
115 Hours, 30 Minutes November 4, 1977 System: LPCI The "A" LPCI/CCSW heat exchanger had tube leakage. Corrective action:
plugged Icaking tubes.
Duration: 549 Hours, 0 Minutes December 3, 1977 System:
Emergency Diesel The Unit 2/3 diesel engine failed to start.
Investigation found the air pressure regulator in the air start system had a blown diaphragm.
Cor-rective action:
replaced regulator.
Duration:
13 Hours, 15 Minutes December 9, 1977 System: ADS Electromatic relief valve 2-203-3H f ailed to open.
Corrective action:
. replaced pilot and adjusted operating lever.
Duration:
9 Hours, 10 Minutes December 12, 1977 System:
LPCI Motor-operated valve 3-1501-3A failed to open via remote signal. The valve was manually cycled with no apparent problem noted. Following this, the valve was cycled using the remote operator with no further problem noted. Corrective action:
none.
Dura *. ion : 0 Hours, 15 Minutes February 7, 1978 System:
LPCI Motor-operated valve 3-1501-5C was closed and could not be reopened.
The valve was manually cycled successfully, followed by remote actua-tion. No further anomalics noted.
Duration: 0 Hours, 20 Minutes March 7, 1978 System: Emergency Diesel The Unit 2/3 diesel engine failed to start.
Investigation showed the air start solenoid to be failed. Corrective action:
replaced solenoid.
Duration:
3 Hours, 0 Minutes March 8, 1978 System:
Emergency Diesel The Unit 2/3 diesel engine experienced an overspeed trip. An investiga-tion showed the injector control IcVer to be sticking. Corrective action:
l freed lever and adjusted governor.
Duration:
2 Hours, 45 Minutes l
l March 30, 1978 System: HpCI Motor-operated valve 2-2301-3 taken out of service to repair steam leak l
(body to bonnet). Corrective action:
installed new seal ring, new packing, and completed same machining of scaling surfaces.
Duration: 90 Hours, O Minutes June 6, 1978 System:
LPCI i
l Motor-operated valve 3-1501-28B would start stroke then operator motor l
would stop.
Investigation showed a defective shaft pin on the limit switch. Corrective action: replaced pin.
l Duration:
18 Hours, O Minutes i
_g_
June 7, 1978 System: LPCI A tube leak was discovered in the LPCI/CCSW heat exchanger. Corrective action:
plugged tubes.
Duration:
55 Hours, 55 Minutes June 30, 1978 System: Emergency Diesel The Unit 2/3 diesel generator cooling water pump thermally tripped.
In-vestigation showed worn pump bearings. Corrective action:
replaced pump.
Duration:
37 Hours, 34 Minutes August 24, 1978 System: Emergency Diesel The Unit 2 diesel engine failed to start due to an air start motor problem.
Corrective action:
replaced cir start motors.
Duration:
2 Hours, 12 Minutes September 22, 1978 System:
LPCI Motor-operated valve 3-1501-20A failed to close.
Investigation showed the contactor stuck at the MCC.
Corrective action:
freed and c1 caned contactor.
Duration:
1 Hour, 10 Minutes September 30, 1978 System: HPCI During operation, the HPCI turbine tripped on low suction pressure.
In-vestigation showed trip due to instrument drift. Corrective action:
recalibrated instrument 2-2360.
Duraticn:
1 Hour, O Minutes l
October 13, 1978 System: Core Spray Motor-operated valve 2-1402-4B would not close against pump head. Lubri-cated stem, cleaned breaker contacts, and checked torque switch setting.
Duration: 4 Hour, O Minutes i
l December 16, 1978 System: Emergency Diesel The 2/3 dicsci engine failed to start.
Investigation showed the time i
delay relay to be dirty. Corrective action:
cleaned relay.
l l
Duration: 4 Hours, O Minutes l
l
[
9_
January 3, 1979 System: HPCI The Unit 2 HPCI turbine failed to start.
Investigation showed an ad-justment problem with the poppet valve and admission valve interlock.
Corrective action: adjusted interlock linkage.
Duration:
9 Hours, 30 Minutes January 11, 1979 System: LPCI Motor-operated valve 2-1501-38B failed to operate.
Investigation showed a broken pinion gear in the operator. Corrective action:
re-placed pinion gear.
Duration:
104 Hours, 10 Minutes February 23, 1979 System: Emergency Diesel The 2/3 diesel generator cooling water pump tripped. Cause - worn bearings. Corrective action:
replaced pump.
Duraticn: 40 Hours, O Minutes March 5, 1979 System: Emergency Diesel The Unit 2 diesel engine failed to start due to failure of the air start solenoid. Corrective action:
replaced solenoid.
l Duration:
6 Hours, 0 Minutes I
l Fbrch 31,1979 System: Emergency Diesel The Unit 2 engine failed to auto-start due to a sticking shutdown sole-noid. Corrective action:
replaced solenoid.
Duration:
8 Hours, 10 Minutes l
April 19, 1979 System:
Isolation Condenser l
The motor for motor-operated valve 2-1301-1 found burned up.
A loose motor lead caused excessive current draw. Corrective action:
replaced motor.
April 25, 1979 System:
Li'C 1 Motor-operated valve 3-1501-38A would not open.
Investigation found broken pinion gear in motor operator. Corrective action:
replaced pinion gear.
Duration:
98 Hours, O Minutes
. _ _ ~
o
. May 30, 1979 System: Emergency Diesel The Unit 2 diesel engine failed to start due to failure of lower air start motor pinion gear to fully engage bull gear. Corrective action:
replaced air start motor.
Duration:
3 Hours, 35 Minutes August 15, 1979 System: HPCI The motor for motor-operated valve 2-2301-4 found burned; cause be-lieved to be moisture related. Corrective action:
replaced motor.
August 24, 1979 System: LPCI Motor-operated valve 3-1501-5B would not close. Cause control trans-former burned up.
Corrective action:
replaced transformer.
Duration:
10 Hours, 30 Minutes September 23, 1979 System:
LPCI Motor-operated valve 3-1501-3A would not operate. Cause - slide wire off track. Corrective action:
realigned slide wire.
Duration:
1 Hour, O Minutes October 4, 1980 System: HPCI i
Motor-operated valve 2-2301-35 failed to open. Cause was moisture in torque switch. Corrective action:
cleaned torque switch.
Duration: 4 Hours, O Minutes December 18, 1979 System: Emergency Diesel l
The air start motors on the Unit 2/3 diesel failed to disengage after engine started. Cause was a loose connection in the speed sensing cir-cuit. Corrective action: repaired connection.
Duration:
3 Hours, 30 Minutes l
l L
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ECC SYSTEM OUTAGE REPORT 4
C OMMori wenz rH EDisou PLANT OuAo c i ti e.s Sra.
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Attachmerit 3 7.l on J La t imn FORM A ECC SYSTEM OUTAGE REPORT UTILITY _ Commonwealth Edison PLANT _
Zion UNIT 1
DATE OF COMMERCIAL OPERATION 12/31/73 REPORT COVERS PERIOD 1/1/75 THROUGH 1/1/80 NUMBER OF DAYS OF COLD SHUTDOWN DURING REPORT PERIOD 494.1 FORMS E COMPLETED FOR FOLLOWING SYSTEliS:
i~Ti HPCI I
i FUCI l
, ISOLATION CONDENSER (one subsystem)
I
! RCIC l
i CORE SPRAY (one subsystem) di SI l
i ADS (one valve)
Q RER l
.RHR SERVICE WATER (one subsystem) i
.ONSITEEMERGENCYPOWER(onesubsystem)
I x ACCU:1ULATORS 4
m S
F0Pe! A ECC SYSTEM OUTAGE REPORT UTILITY Commonwealth Edison PLANT _
Zion UtilT 2
7.
DATE OF COMMERCIAL OPERATION 9/17/74 REPORT COVERS PERIOD 1/1/75 THROUGH 1/1/R0 NUMBER OF DAYS OF COLD SHUTDOWN DURING REPORT PERIOD 490.7 FORMS B COMPLETED FOR FOLLOWING SYSTEMS:
i ISOLATION CONDENSER (one subsystem)
I iRCIC i
i CORE SPRAY (one subsystem)
L_LisI l
i RHR SERVICE WATER (one subsystem) i
.ONSITEEMERGENCYPOWER(onesubsystem)
I i ACCU:!ULATORS DATE 12/18/ft?
D.B.
FORM B ECC SYSTEf1 OUTAGE REPORT PLANT Zion UNIT 1
SYSTEM Accu.mul a to r PAGE 1 0F in ALLOWABLE OUTAGE TIME FOR SYSTEM 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OUTAGE DURATION OF DATE OUTAGE (DAYS)
CAUSE 1/13/76 1
Unit 1 Accumulators - renair SI8RRO, SI8875B 6/24/76 2
1D Accumulator discharge vlv. - reoair valve 9/16/77 58 U-l Accumulators - modifications s
DATE 12/10/prgy a,a,
FORM B ECC SYSTEM OUTAGE REPORT PLAtiT Zion
_UtilT 1,2 SYSTEM SI PAGE 2 0F 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 days OUTAGE DURAT10t1 0F DATE OUTAGE (DAYS)
CAUSE 2/4/75 1
1A & IB SI pumos - oil change & lubrication 2/4/75 1
l?!OV-SI8809A - repair breaker 3/9/75 2
liMOV-SIPPllB - reoair valve 4/11/75 1
2MOV-SI8812A,B - repair RHR7083 4/15/75 1
2"OV-SI8812A,B - repair RHR Suction Relief 9/10/75 1
2?10V-S I 8 80 9 B - renair SI flow orifice to DCS 1000 2A 9/15/75 2
~ 2"OV-SI90llA - recair nackina leak 1/20/76 4
2"O-S I 8 8 0 9 B - renair 2SI-8957A 2/19/76 1
l? TOV-SI8814 - recair valve s
4/16/76 1
l?'OV-SIPP09A - reoair valve 4/19/76 1
1"OV-SIPP09B - renair leakage on ISI-P457B and orifice flanges 4/20/76 1
l'tOJ-SI8809A - repair leakage on ISI-P957A and orifice flanges 4/23/76 1
1A, 1B SI pumps - renair counlings 6/8/76 1
2A SI numo - reonir nuro 7/1/76 1
1B SI oump - reoair breaker 2/7/77 1
2A, B SI Punos - reoack bearings DATE 12 /IP/ 80BY B B-
FORM B ECC SYSTEM OUTAGE REPORT PLANT Zion UNIT 1,2 SYSTEM SI PAGE 3 0F 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 davr.
OUTAGE DURATION OF DATE OUTAGE (OAYS)
CAUSE 2/6/77 4
2P!OV-SI8811A - repair nacking 2/9/77 1
2MOV-SI8811B - renair valve 2/10/77 1
2MOV-SI8811B - renack 2/13/77 1
2POV-SI9011A - renair valve 2/18/77 1
25 TOV-SI8923A - remove spare Aux, contact 9/12/77 3
1A, IB SI pumos - modification 11/10/77 1
'1MOV-SI8813 - repair valve 2/7/78 3
2A SI oumn - inspect breaker 3/21/78 1
2.*50V-SI8881A-valve disassembly s
3/23/79 2
2A, 2B SI pumos - test relief valves 4/12/79 3
2MOV-SI8000D - reolace motor DATE 12/18/8GY B.B.
4
FORM B 4
ECC SYSTEM OUTAGE REPORT PLANT Zion UNIT 1,2 SYSTEM IIPCI PAGE 4 OF 10 ALLOWABLE OUTAGE TIME FO7 SYSTEM 7 days 0ViAGE DURATION OF l
DATE OUTAGE (DAYS)
CAUSE 3/2/75 19 BIT - reoair heater 3/2/75 16 1A Charging Pump - repair 3/6/75 1
l? TOV-SI8804A - Allow electricians to move conduit 4/1/75 3
1A Charging Pumo - reoair 4/4/75 1
1A Charging Purp - lubrication 4/10/75 1
2A Charging Pung - discharge flange leak 10/27/75 2
2A Charging Pump - repair ouno 10/31/75 1
1A Charging Pump - replace relay 11/3/75 2
2B Charging Puno - recair oung s
1/16/76 5
2A Charging Pur - reoair seal 1/24/76 1
Unit 2 BIT - flush BIT 1,'25/76 5
Unit 2 BIT - recair BIT inlet valve 2/2/76 3
Unit 2 BIT - reoair BIT inlet valves 2/24/76 1
l? TOV-SIPS 01A - repair valve 2/24/76 1
2B Charging Pumo - renair seal 3/24/76 9
Unit 1 BIT outlet viv. - recair packing leak DATE 12/lE/80BY B 3-
1 FORM B ECC SYSTEM OUTAGE REPORT PLANT Zion UNIT 1,2 SYSTEM llPCI PAGE 5 Of 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 davs OUTAGE DURATION OF CAUSE DATE OUTAGE (DAYS)_
4/23/76 3
1A Charging Pumn - reoair counlina 4/26/76 1
IB Charging Puno - repair coucling 4/28/76 3
1A, 1B Charging Pumo - CVCS niping modification 5/22/76 1
1A, 1B Charging Punns - rerove suction strainers 6/2/76 1
1A Charging Punn - renair pressure switch 10/20/76 1
2A Charging Pumn - breaker insnection 2/6/77 34 U-2 VCT & Charging Pungs - VCT nodifications 2/6/77 21 2A, 2B Charging Purns - renack conoling 2/6/77 21 U-2 BIT - recair 2/6/77 23 2".O'J-S I 8 801B - repair "O'?
1 2/10/77 15 2"OV-SIB 803A &
B-renair valves i
2/18/77 9
2 'OV-SIS 801A - disconnect motor 2/19/77 8
2"OV-SIB 803A,3 - disconnec-motors 2/24/77 7
2A,B Charging Punos - lubrication 2/25/77 4
2"OV-SIS 801A,B, 2:OV-SIB 8n3A - limitorque check DAT E_2 /19 / 80 BY33-l
FORM B ECC SYSTEM OUTAGE REPORT PLAf1T Zion UtilT 1,2 SYSTEM IIPCI PAGE 6 0F 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 days OUTAGE DURAT10tl 0F DATE OUTAGE (DAYS)
CAUSE 3/2/77 6
U-2 BIT - hydro test 3/2/77 1
1A Charging Pung - change oil 3/21/77 1
2A Charging Pung - remove suction strainer 3/22/77 1
2B Charging Pump - repair seal & remove suction strainer 5/23/77 4
2B Charging Pung - repair seal 7/25/77 1
1A Charging Pumo - inspection & recair 8/18/77 1
~ 2B charging Pump - heat calibration test 10/3/77 2
1B Charging Pump - renair and alignment check 10/5/77 7
1A Charging Pump - repairs & alignr.ent check 10/6/77 25 IB Charging Pump - repair'ing pressurizer Aux. snray valve 10/12/77 2
1A, 1B Charging Pumps - lubrication 10/25/77 2
U-1 inlet & outlet BIT valves - repack valves 11/5/77 3
1B Charging Pump - alignment 11/11/77 1
2'10V-SIO801B - repair valve 11/11/77 3
1A Charging Pump - coupling insocction 11/14/77 3
2B Charging Pumo - repair DATE 12 /18 /80BY B.B.
FORM B ECC SYSTEM OUTAGE REPORT PLANT Zion UNIT 1,2 SYSTEM HPCI PAGE 7 0F 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 davs OUTAGE DURATION OF DATE OUTAGE (DAYS)
CAUSE 2/7/78 3
2B Charging Pumo - inspect breaker 2/10/78 2
2MOV-SI8800D - repair motor 2/21/78 2
U-2 BIT - work on inlet & outlet valves 3/1/78 10 U-2 BIT - repair BIT inlet & outlet valves 3/3/78 7
2MOV-SI8801A - disconnect for maintenance 3/5/78 1
1A Charging Pump - repair bearing 3/5/79 7
'2A Charging Pumo - eliminate leakoff to system 3/6/78 6
2A, 2B Charging Pump - reolace 2SI-8925 valve 3/7/78 2
2A, 2B Charging Pump - lubrication s
3/25/78 2
U-2 BIT - repair BIT i n le't valves 3/29/78 8
U-2 BIT - repair BIT inlet & outlet valves
(
3/30/78 2
2:10V-S I 8 8 01B - remove valve 1
+
9/14/78 1
1A Charging Pumo - oil change 10/8/78 2
U-l BIT - repair relief valve 10/10/78 4
U-l BIT - repair relief valve 3/22/79 3
2A Charging Pumn - replace inboard seal DATE12 /18 / 80 BY B.B.
FORN 8 ECC SYSTEM OUTAGE REPORT PLANT Zion UNIT 1,2 SYSTEM HPCI PAGE 8 0F 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 days OUTAGE DURATION OF DATE OUTAGE (DAYS)
CAUSE 3/22/79 1
2C Accumulator - test relief valve 4/4/79 3
U-2 BIT outlet valve - repair leak 4/4/79 2
2MOV-SI8801A - repair body to bonnet leak 4/17/79 7
2MOV-SI8800D - repair motor 5/14/79 2
1B Charging Pump - reolace outboard seal 9/27/79 1
1B Charging Pumo - shaft testing 9/30/79 3
- IB Charging Pumo - reolace outboard radial bearing 10/5/79 1
1A Charging Pumo - shaft hardness testing DATE 12/18/Prgy 3.3,
FORM B ECC SYSTEM OUTAGE REPORT PLANT Zion UNIT 1 & 2 SYSTEM RIIR PAGE 9 0F 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 davs OUTAGE DURATION OF DATE OUTAGE (DAYS)
CAUSE 4/9/75 1
Relief valve 2RII8708A inoperable 4/11/75 1
Relief valve 2RH8708B inoperable 4/15/75 l
RHR suction relief valve inoperable 6/3/75 1
Relief valve IRH8708A inoperable 8/14/75 1
Valve loop calibration on 2MOV-RH8701 8/18/75 1
Valve calibration on'2MOV-RH8701 3/11/76 1
' Test on IB RHR Pump Switch 6/3/76 1
2MOV-RH8703 inoperable 9/27/76 3
2A RHR Pumo inocerable 10/6/76 1
Leak on RHR System Relief Valve 10/20/76 1
Inspection on 2A RHR Pump Breaker 6/4/77 1
2"OV-RH87008 inoperable 8/17/77 1
2".OV-RH8700B inoperable 4/21/78 1
1MOV-RH8700B inoperable 2/20/79 3
2A RHR Pump inoperable DATEll/10 / 80 BY A.
Panagos
FORM B ECC SYSTEM OUTAGE REPORT PLANT Zion UNIT 1 & 2 SYSTEM RilR PAGE 10 0F 10 ALLOWABLE OUTAGE TIME FOR SYSTEM 7 days OUTAGE DURATION OF DATE OUTAGE (DAYS)
CAUSE 6/4/79 1
2B RIIR Pump inoperable 6/10/79 4
2B RilR Pump inoperable 12/15/79 5
Repair on lA RIIR miniflow DATE 11/10/80BY A.
Panagos