ML18051B250
| ML18051B250 | |
| Person / Time | |
|---|---|
| Site: | Palisades, Big Rock Point, 05000000 |
| Issue date: | 01/28/1985 |
| From: | Vandewalle D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GL-84-24, NUDOCS 8502050535 | |
| Download: ML18051B250 (18) | |
Text
- - j consumers Power David J VandeWalle company Director of Nuclear Uce11.Jing General Offices
- 1945 West Parnell Road, Jackson, Ml 49201 * (517) 788-1636 January 28, 1985 Director, Nuclear Reactor Regulation US Nuclear Regulatory Connnission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT .PLANT -
DOCKET 50-255 - LICENSE DPR PALISADES PLANT -
RESPONSE TO GENERIC LETTER 84 EQ PROGRAM CERTIFICATION Generic Letter 84-24, dated December 27, 1984 notified all licensees that they were required to provide written certification that:
(a) the utility has in place and is implementing an Environmental Qualification (EQ) Program that will satisfy the requirements of 10 CFR Section 50.49 within the currently approved schedule for the plant without further extension; (b) the plant has at least one path to safe shutdown using fully qualified equipment, or has submitted a justification for continued safe operation (JCO) pending full qualification of any equipment not fully qualified; and (c) all other equipment within the scope of 50.49 is either fully qualified or a JCO has been submitted pending full qualification.
In response to item (a) - Consumers Power Company has in place and is implementing an EQ Program at each of our nuclear plants (Palisades and Big Rock Point). These programs and their schedules for full implementation have been described in our previous submittals (including our latest submittals of January 15, 1985 for the Palisades Plant and January 7, 1985 for the Big Rock
.. Point Plant). Descriptions of these submittals with dates are attached to this letter (see Attachments 2 and 3). Because, we still have equipment that has not been fully qualified it is necessary for us to request extensions for both plants to November 30, 1985. It is hoped that we will not have to
. .,-*' request a further extension beyond November 30, 1985 as provided in 10CFR50.49.g.
In response to Item (b) - Consumers Power Company believes that our EQ
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! Programs ensure that our plants can be operated safely and be brought to a safe shutdown using equipment that is qualified or has a current JCO. The ~
OC0185-0117A-NL0i 8502050535 850128
.PDR ADOCK 05000155 AAJ-*. g~.
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Director, Nuclear Reactor Regulation 2 Big.Rock Point and Palisades. Plants Generic Letter 84-24
- January 28, 1985 JCO's for Palisades Plant have been submitted previously as docketed material See Attachment 1 for the JCO's for Big Rock Point.
In response to Item (c) - Consumers Power Company considers all equipment determined to be within the scope of 10CFRS0.49 is either fully qualified or Justifications for Continued Operation have been provided.. The Justifications for Continued Operation for Big Rock Point Plant have been revised to include additional items not included in our January 7, 1985 submittal. These items are the result of additional document reviews and on-site verifications, in our continuing upgrade program. **
In developing and implementing our EQ Programs, we have ascerta~ned that we have addressed the relevant aspects of NRC IE Bulletin 82-04 and IE Informa-tion Notices 82-11, 82-52, 83-45, 83-72, 84-23, 84-44, 84-47, 84-57, 84-68 and 84-78. Our existing Administrative Controls provide for the review and*
incorporation of these aspects into our EQ Programs.
Consumers Power Company letter dated October 5, 1984 (Docket 50-255) requested
- . an extension for our Palisades Plant from March 31, 1985 to at the latest, November 30, 1985 for installation of the remaining qualified equipment. A
..... similar extension request is planned for our Big Rock Point Plant and will be
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submitted in February.
It is our intention to start all remaining required EQ modifications no later than November 30, 1985 for both of our plants. These modifications could take place earlier if the condition of a planned or unplanned outage of sufficient duration happens. On the other hand,. the occurrence of a lengthy unplanned outage prior to the delivery of the remaining pieces of qualified equipment may preclude our ability to meet the November. 30, 1985 date. Consumers Power Company recognizes that any request for an extension past the November 30, 1985 deadline exceeds the authority of the Director of the Office of Nuclear Reactor Regulation and will require the approval of the Commission itself.
Pending your approval of the extension requests, our 1985 refueling outage is planned for Palisades in November 1985, and for Big Rock Point in July 1985.
Director, Nuclear Licensing CC Administrator, Region III, USNRC NRC Resident Inspector - Big Rock Point & Palisades Plants Attachments OC0185-0117A-NL04
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CONSUMERS POWER COMPANY Big Rock Point & Palisades.Plants Docket 50'.""155 & 50-255 Licenses DPR-6 & DPR-20 Response to Generic Letter No 84-24 dated December 27, 1984
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At the request of the Commission and pursuant to the Atomic Energy Act of 1954 ....
and the Energy Reorganization Act of*1974, as amended, and the Commission's ...--. :*- .
Rules and Regulations thereunder, Consumers Power Company submits our.respon~e to NRC letter dated December 27, 1984, e~titled, "Certification of Compliance to 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants (Generic Letter 84-24)." Consumers Power Company's response is dated January 28, 1985.
CONSUMERS POWER COMPANY Byfih ....._~~~.-J-.--r.~-
R B DeWitt, Vice President Nuclear Operations Sworn and subscribed to before me this 28th day of January, 1985.
Sherry L D r ey, Notary son County My commission expires November 5, 1986 SHERRY LYNN DURFEY Notary Public, Jackson County, Mlclt.
My Ccrr.mis~!cn 8:pir:;;~ Nev. 5, 1985 "l
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ATTACHMENT 1
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Consumers Power Company .... ..
Big Rock Point Plant Docket 50-155
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BIG. ROCK POINT .
ELECTRICAL EQUIPMENT QUALIFICATION JUSTIFICATION FOR CONTINUED OPERATION January 28, 1985 6 pages IC0185-0117B-NL04
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Attachment 1 BIG ROCK POINT - ELECTRICAL EQUIPMENT QUALIFICATION JUSTIFICATION FOR CONTINUED OPERATION TER Item No. 61: M0-7051 and M0-7061 Cables - Primary Core Spray Valves The cables associated with M0-7051 and M0-7061 are presently unqualified; however, this equipment has qualified redundant equipment to perform the safety function. M0-7070 and M0-7071, the Backup Core Spray Valves, are the redundant valves. Criterion i- of 10CFR50.49(i) is therefore satisfied.
TER Item No. 5: M0-7066 Water Valve Motor Starter - Actuates Post Incident Heat Exchanger Cooling
- i The valve , M0-7066, .has a fully qualified redundant valve, M0-7080, which is capable of performing the same function. Criterion 1 o.f 10CFR50.49(i) is therefore satisfied.
TER Item No. N/A: SV-4897 - Actuates Demin Water to the Containment Building Valve, CV-4105 This solenoid valve isolates demineralized water to the containment building by closing CV-4105 via manual operation from the control room. It is backed up by a self-actuating check valve which is located inside containment. The check valve redundancy meets the Criterion 1 of 10CFR50.49(i).
TER Item No. 32: LT-3171, Including Terminal Block in Junction Box JB/LT-3171, Provides a Signal for Containment Water Level Indication This level transmitter has a fully qualified redundant transmitter LT-3175 which is capable of performing the safety function. Criterion 1 of 10CFR50.49(i) is therefore satisfied.
TER Item No. 33: FT-2161, FT-2162, FT-2163, FT-2164, Provides a Signal for Flow Indication, Indication for Containment and Core Spray Flow
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These flow transmitters are to be replaced with qualified equipment;
' presently, other equipment is capable of providing the required function.
In the event of failure of the reactor core spray flow transmitters (FT-2162 and FT-2163) during a line break event, core spray flow can be inferred by
- ..~ verification of the fire main pressure availability (via the RDS Annunciator Panel and Fire System Annunciator Panel) plus opening of the core spray valves
- l by observation of the valve position lights. These lights are integral to the
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.**.motor operator ~hich i~ q~~lified.
- Upon ~nter:l.ng the recirculation mode~ b~th .*
containment spray lines and one core spray* line is closed. Co.re spray flow can then be determined by core spray pump availability (pump indicating .. *: .,.*,_, ...
lights) and by monitoring pump outlet pressure, that is annunciated (via - *:*~.
PS-638 which is qualified) in the control room. *Criterion .1 of 10CFR50.49(i)
. is therefore satisfied~
Likewise, contairiment spray flow can be inferred, in the event of failure of the _containment. spray flow transmitters (FT-2161 and FT-2164) by verification *~. ~: *. *~* .: --
of* fire main pressure availability plus opening of the. containment spray
- valves by.operation of the valve position lights (these light switches are '; '*. -
integral to the motor operator which is qualified) and by monitoring contain-ment pressure with a qualified instrument. Core spray flow analysis has shown that sufficient core spray flow exists assuming a break in either core spray*
line. *Isolation of a core spray line with a break is only required in the recirculation mode. At this time, if a reactor core spray flow transmitter has failed, adequate core spray flow can be determined by monitoring reactor vessel level (with qualified instruments) as the core spray line break would be above the reactor. core.. Core spray pump availability can be determined by pump indicating lights and by monitoring pump outlet pressure, with a qualified instrument. Therefore, the plant can maintain safe shutdown in the absence of the unqualified equipment. Criterion 1 of 10CFR50.49(i) is there-fore satisfied.
Item: Containment Isolation Position Switches POS - 6618 POS - 6629 POS - 9101 6623 6653 9102 6624 6654. 9103 6626 6655 9104 6628 6660 The.above position switches provide operator information to show their respective contaimilent isolation valves are c*losed. Although the position switches are presently unqualified (they have recently been added to the EEQ List as required equipment), the valves for which they provide indication are either qualified equipment or have redundant qualified equipment to fulfill their function.
Associated with the above position switches are containment isolation valves normally one valve inside and one valve outside containment. The ventilation isolation valves are both outside. (Other exceptions are noted in A. and B.
below.)
The environment inside containment is assumed to cause failure of the position switches inside containment. However, outside containment in both the steam tunnel area and air shed, where the position switches are located, the immediate post accident environment remains normal. Both temperature and radiation exposure will increase but no immediate effects to equipment are expected to occur due to these parameters. As the containment isolation valves close quickly in the event of a line break, on a containment high pressure signal at i1:1.psig or on a:low reactor water level signal, the NU0185-0110C-NL04
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position switches outside containment, although not presently qualified, would still.be expected to operate in the immediate short term.
An operator action following a break is to verify that the containment isola-tion valves are closed. - Once the operator has verified containment penetration lines have isolated via the position indication, a loss of the indication should not affect further judgement because lines are provided with qualified valves or have required qualified redundance for their function~
Loss of the position indication does not affect.the valves ability to remain closed. Until qualified position indication is provided the operators have_
been instructed via an Operations Memo that the position indication for valves inside containment is not reliable. Criterion 1 and 3 of 10CFR50.49(i) are .. . . ..- . *~
therefore satisfied. ......
Noted above were two exceptions to the isolation valve inside - outside design. They are:.
A. The clean-up demineralizer resin sluice valves. (Position switches 6653, 6654, and 6655 and Terminal Block in Junction Box 100 for Position Switches 6654 and 6655.)
These valves are normally closed per procedure during power operation (as is the outside manual isolation valve VCU-13) except in the case of transferring resins. In the remote event that a break occurred during the time resins were being transferred, these qualified inside isolation valves would close on a containment isolation signal.
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B. The treated waste return to containment (CV-4049)
(Position switch 6626)
This valve (CV-4049) is backed up by a check valve. CV-4049 is normally maintained closed per the procedure.
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-:I For both A. and B. above, qualified position indication would not be available
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~~i but the operator would be aware of system status. Again, an Operations Memo j has been issued identifying the position indication for these control valves
- ...c inside containment as unreliable and for both of these systems the operator is instructed to initiate action to close or check closed the manual isolation valves outside containment. This administrative action meets Criterion 3 of 10CFR50.49(i).
-' . Item: POS - 6680 through 6687 - Reactor Depressurization System Valves
.) Position Switches If these position switches should fail they will not affect the ability of the valves to close. The RDS is designed for single failure and since the valves are qualified, the safety function is assured regardless of the position indication. An operator could be misled if the position indication is erroneous; however, his on-ly- available action is to initiate RDS manually.
NU0185-0110C-NL04
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- The operator is by procedure instructed to take. 'this action i f all the RDS ,
- initiating signals have been satisfied and RDS hasn't actuated automatically.
Parameters including.reactor vessel pressure, containment pressure and
, ***indication that the core spray valves have opened would assure the operator** .. *'.' ..
. that RDS,has*actuated. Also actuation of RDS is expected to be clearly audible in the .control room. Criterion 5'of 10CFR50.49(i) is therefore satisfied.
Item: POS 6649 - Position Switch for Demin Water Isolation Valve *.
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The Demin Water isolation val~e is.a ~anu~lly ~per~ted valve (see JCO for*
SV-4897), backed up by a self~actuating check valve.* The position switch and valve are located outside containment. Failure of the position switch will not degrade the safety function of the valve. Temperature, pressure, and' , -* .. * ..
relative humidity all remain at ambient conditions outside containment in the short term following a break. The tottl integrated 30-day radiation exposure at the valve location is only 2.0 x 10 rads. The short term dose would have no effect on. the position switch. The mild environment at the position switch immediately following a break event assures that the operator will have adequate time to check the valve position indication, as required by proce-dure, and assure valve closure prior to the time when failure of the switch could cause misleading information. If the operator is uncertain, he could check the valve position at the valve or close other manual valves in the system. Criterion 5 of 10CFR50.49(i) is therefore satisfied.
New Item: Stanwick Terminal Blocks in Junction Box 153 and 154 The terminal blocks provide cable connections for motor operated valve M0-7072 (motor, limit switch and position indication lights) and differential pressure indication switch PDIS-7814. The terminal blocks and junction boxes are located in the sphere ventilation room and in the core spray pump room, respectively.
The line containing M0-7072 and the basket strainer, for which PDIS-7814 provides differential pressure indication, is a redundant supply line for the core sprays or enclosure sprays. The valve has no automatic function and would only be used in the unlikely event of a failure of the primary supply line. Because this line is redundant to the core spray supply line, containing qualified valves M0-7070 and M0-7071, and enclosure spray supply line containing M0-7064, the terminal block and its attached cable for M0-7072 and PDIS-7814 are also redundant components, therefore Criterion 1 of 10CFR50.49(i) is satisfied.
New Item: Terminal Block in Junction Box for PDr'S...,7814 The terminal block provides cable connections for differential pressure indicating switch PDIS-7814. The terminal block is located in the core spray pump room. The line containing the basket strainer, for which PDIS-7814 provides indication, is a redundant supply line for the core sprays or enclosure sprays. Because this line is redundant to the core spray supply NU0185-0110C-NL04.
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line, which includes qualified valves M0-7070 and M0_.:7071 and *enclosure.spray supply line containing M0-7064, .the terminal block and its attached cable for ' **-~.
. PDIS~7814 are also redundant* components. *Criterion. I of 10CFR50.49(i) is
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New Item: Terminal Block in Junction Box for SV-4895 The terminal block and environmentally qualified solenoid are located outside .*
- containment in the turbine building pipe tunnel.. The immediate post. accident .
environment remains _normal in this area. The solenoid valve controls the air.*
supply to the containment isolation valve cv~4102*for the reactor enclosure.
clean sump pump discharge *. The solenoid is de-energized on a safety system ::
signal on high enclosure pressure. The terminal block contains only wire-connections for SV-4895; therefore since the valve will be de-energized early in the event when the environment is mild, the circuit will remain qualified even with an unqualified terminal block. The failure of the terminal block from potential shorting across the leads is not a consideration because the circuit will be de-energized by the safety system signal and because no other voltage sources exist in the junction box. Criterion (4) of 10CFR50.49(i) is therefore satisfied.
New Item: Stanwick Terminal Block in Junction Box for SV-4869, SV-4891 and SV-4900 The terminal block and solenoids are located inside containment. Solenoid valve SV-4869 controls the air supply to containment isolation valve CV-4031, the reactor enclosure clean sump pump discharge. Solenoid valve SV-4891 controls the air supply to containment isolation valve CV-4025, the reactor enclosure dirty sump pump discharge. Solenoid valve SV-4900 controls the air supply to CV-4050, a poison system control valve. SV-4869 and SV-4891 are environmentally qualified solenoid valves and will be de-energized by the safety system on high enclosure pressure. SV-4900 is not required to be qualified per 10CFR50.49. Solenoid valve SV-4900 is a normally de-energized valve; it would not*be energized in a LOCA or MSLB event, therefore there is not potential for shorting across the terminal block and causing the isolation valves to open since no voltage sources _would exist at the time in the junction box. Criterion (5) of 10CFR50.49 is therefore satisfied.
The interior enclosure clean and dirty sump pump isolation valves are redundant to the exterior isolation valves. The exterior isolation valves are controlled by solenoid valves which have qualified circuits. The dirty sump pump discharge line isolation valve solenoid valve, SV-4896, circuit' is qualified and the clean sump pump discharge line isolation valve solenoid valve, SV-4895, circuit is qualified as described in the preceding JCO.
Criterion (1) of 10CFRSO. 49 is *therefore satisfied as alternate qualified equipment is available.
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- T~rminal . ~lock' "TA". for SV-9l51 -: *vac~um Rel.ief Solenoid Valv~ .". . . :*._:.::F_:\:;
Two redundant: sets of solen~id ~alves.pr~vide. containment v~cuum relief_.
capability. One set,- *redundant* to the one containing SV-9151, is fully * . . :;*: *.'.J'. *'
qualified and capable of performing the safety function~ Criterion 1 of.
- 10CFR50.49(i) .is therefore satisfied. : ....
- .**.New Item TER Item No. 61 and* 1: M0-7068 Cable Redundant Containment Spray
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. Valve *".*:
The valve, M0-7068, is the.backup containment spray valve and is redundant to* . '
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the fully qualified containment spray valve M0-7064. Criterion 1 of 10CFR50.49(i) is therefore satisfied.
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.. ATTACHMENT 2 * ... ~.
Consumers Power Company Big Rock Point Plant Docket 50"'."155
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- .r CONSUMERS POWER COMPANY ELECTRICAL EQUIPMENT QUALIFICATION PROGRAM BY DOCKETED SUBMITTAL January 28, 1985 3 pages IC0185-0117B-NL04
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.. CONSUMERS POWER COMP ANY ***.-, .
.ELECTRICAL EQUIPMENT QUALIFICATION PROGRAM BY DOCKETED SUBMITTAL
,. ,. I Date Descriptfon 2/24/78 Response to Letter Dated December 23, 1977: Environmental Qualification 3/23/78 (Corrections and additions to above letter) 8/03/78 (Comments to Petition for Reconsideration from the Union of Concerned Scientists (UCS).)
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- 1 9/18/78 Electrical Equipment Qualification Summary Sheet 10/10/78 (Letter enclosing electrical diagrams omitted from previous package.)
10/11/78 SEP - Topic III-12 "Environmental Qualification of SafE7t~~Related.
Electrical Equipment.
11/30/78 Response to Letter Dated September 6, 1978: Environmental Qualification (SEP Topic III-23) 12/20/78 Correction to Letter dated November 30, 1978: Environmental Qualification (SEP Topic III-12) 6/30/80 SEP Topic III-12 Environmental Qualification: Submittal of Requested Information 9/02/80 Qualification of Electrical Equipment 9/19/80 Anchorage and Support of Safety Related Electrical Equipment 10/31/80 Response to Environmental Qualification of Electrical Equipment
)
': 11/26/80 Clarification of October 24, 1980, Orders Concerning Electrical
~quipment Qualification 1/30/81 Revision of Electrical Qualification of Safety-Related Electrical Equipment 3/02/81 Response to Environmental Qualification of Electrical Equipment 9/03/81. Environmental Qualification of Safety-Related Electrical Equipment (Response to 5/28/81 letter not 6/1/81 as stated in this letter)
NU0185-0117A-NL04
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- ... **. 4/01/82 Response to Request for Additional Information - Environmental
- *.. Qualification of Safety-Related Electrical . Equipment
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4/30/82 Status' Report Submittal - Electrical *Equipment Qu~lificatfon .(EEQ)-
- 6/23/82 * .
- Corrections' to .April 30, *.1982 Electrical Equipment Qualification
- .(EEQ)
- Status Report . *..
- 3/01/83 Additional Information.to Substantiate Radiation Environment for Equipment Qualification 3/10/83 Electrical Equipment Qualification - Clarification of Pressure Switches Test Results 3/18/83 Integrated Assessment of All Open Issues (Including Environmental Equipment Qualification) and Generic Letter 82-33 Issues and Schedule for Issue Resolution 5/31/83 Environmental Qualification*of Safety-Related Electrical Equipment -
Response to Thirty (30) Day Request 6/01/83 Integrated Assessment of Open Issues and Schedule for Issue Resolution (Including Environmental Equipment Qualification and Generic Lettei 82-33 Issues) 9/30/83 Environmental Equipment Qualification - Results of Failure Modes and Effects Analysis 11/7 /83 Living Schedule Update
- : 12/15/83 Environmental Equipment Qualification - System Components Evaluation Worksheets for 1983 Refueling Outage Modifications
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- .! 6/01/84 Request for Extension of the Submittal Date for Integrated Assessment Issue 36 - Environmental Qualification of Electrical Equipment (EEQ)
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.:.i 6/29/84 Environmental Qualification of Safety Related Electrical Equipment (Integrated Assessment Issue No 36) - Request for Extension of 10 CFR 50.49 Schedular Requirements and Additional Qualification Information
,;j 7/18/84 Environmental Qualification of Safety Related Electrical Equipment
- , (Integrated Assessment I~sue No 36) Revised Justifications for Continued Operation 8/09/84 Submittal of Application fee.- 10CFRS0.49 Extension Request of June 29, 1984 NU0185-0117A-NL04
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~*,. Atta~hm~~t* 2 - .Big Rock Point Pl~ni * . '*<:, :*
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- 'Date* '*
. Description
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8/27/84 . Environmental Equipment Qualification (EEQ) Response to Request-for
- *. *Additional Information. *, *. ,, . .*.-*
10/31/84- Electrical Equipment Qualification *(EEQ) Program_
1/07/85 Electrical Equipment Qualification (EEQ) Program Additional
_Information j
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NU0185-0117A-NL04_
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- ATTACHMENT 3.
Consumers Power Company *.*:-
Palisades Plant Docket 50-255
- i CONSUMERS POWER COMPANY
.; ELECTRICAL EQUIPMENT QUALIFICATION PROGRAM
- .1.*; BY DOCKETED SUBMITTAL January 28, 1985
.i 3 pages IC0185-0117B-NL04
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PALISADES PLANT ... ,.< .... **.:: *- -.: ..
. CONSUMERS POWER COMP ANY .
- ELECTRICAL EQUIPMENT QUALIFICATION PROGRAM
. .. BY DOCKETED SUBMITTAL Date Description
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3/23/77 **.Submerged Electrical .Systems Study
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11/23/77 Union of Concerned Scientists Petition for Emergency & Remedial
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- 2/02/78 Submerged Electrical Equipment - (Update of Bechtel Report Submitted March 23, 1977) 2/24/78 SEP Topic III Environmental Qualification of Safety-Related Electrical Equipment 4/12/78 SEP Topic III Environmental Qualification of Safety-Related Electrical Equipment (Revision) 8/03/78 Union of Concerned Scientists Peitiion for Reconsideration dated May 2, 1978 10/10/78 SEP Topic III-12 EEQ - Electrical Diagrams 10/11/78 SEP Topic III Environmental Qualification of Electrical Equipment 11/30/78 SEP Topic III Environmental Qualification of Electrical Equipment 1/19/79 SEP Topic III Environmental Qualification of Electrical Equipment (Revision of List) 7/07/80 Response to Franklin Institutes Technical Evaluation of Environmental Qualification of Electrical Equipment 9/02/80 Environmental Qualification of Ele~trical Equipment 10/30/80 Revision 1 to October 7, 1980 Environmental Qualification of Electrical Equipment 11/26/80 Clarification of October 24, 1980 'Orders' Concerning Electrical
... Equipment Qualification
' 2/23/81 Response to Environmental Qualification of Safety-Related Electrical Equipment 6/11/81 Revision 2 to Octobe~ 7, 1980 Environmental Qualification of Electrical Equipment j NU0185-0117C-NL04
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- Description* *
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' 9/03/81 Environmental Qualification of Safety-Related Electrical Equipment
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12/04/81 Environmental Qualification of Safety-Related Electrical Equipment.
(Complete Revision) 2/12/82 Environmental Qualification of Safety-Related Electrical Equipment
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. Environmental Qualification ..of.* Safety~Rel~ted Electrical Equipment 2/24/82 ' '. '::****
- Status Summary of EEQ Work to be Submitted in March 1982 . ~*
3/03/82 . Environmental: Qualification of Safety-Related Electrical Equipment Status. Report & Revision 2 3/15/82 Environmental Qualification of Safety-Related Electrical Equipment Status Report & Revision 2 of March 3, 1982 Submittal (Additional Information) 3/25/82 TM! Action Plan - Environmental Qualification of Safety-Related Electrical Equipment (Additional Information) 5/21/82 Environmental Qualification of Electrical Equipment - Additions to Revision 2 of March 3, 1982 5/25/82 Environmental Qualification of Safety-Related Electrical Equipment
- Calibration 6/30/82 Environmental Qualification of Safety-Related Electrical Equipment
- Status Report 5/06/83 Response to Ten Day Information Request on Environmental Qualification of Safety-Related Electrical Equipment 5/20/83 Environmental Qualification of Safety-Related Electrical Equipment Response to SER Open Items & 10CFR 50.49 Rulemaking 10/03/83 Electrical Equipment Qualification - Date Extension for Response on 2400 Volt Motors 2/14/84 Environmental Qualification of Safety-Related Electrical Equipment (Additional Information) 6/15/84 Environmental Qualification of Equipment Important to Safety
. i (Response to Request for Additional Information) 10/05/84 Request for Delay in EQ Replacement Schedule - Due to Our Desire to Have the EQ Outage and 1985/1986 Refueling Outage 11/30/84 Environmental Qualification of Equipment Important to Safety ~
Additional Information - Identify to NRC That All JCO's for EQ Equipment Planned for Installation During *Outage Will Start No j
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Palisades Plant . ' ..
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.. * .. . *.. ** Description* **
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12/19/84 .Submittal of Feed - Extension Request for Electrical Equipment : .'.;
Qualification *for a. Requested Extension of the Deadline Date for Environmental Qualification of Certain Electrical Equipment for Palisades
- l/.15/85 EEQ Replacement Schedule - Additional Information
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