ML17325A182
| ML17325A182 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/25/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| AEP:NRC:0838Z, AEP:NRC:838Z, NUDOCS 8707010205 | |
| Download: ML17325A182 (19) | |
Text
4 p
REQULAT INFORNATION DISTRIBUTlQN STEN (BIDS)
~f
'CCESSION NBR: 8707010205 DOC. D*TE: 87/06/25 NOTARIZED:
NO DOCKET 0 FACIL: 50-315 Donald C.
Cook Nuclear Power Plant'nit 1>
Indiana 8c 05000315 50-316 Donald C.
Cook Nuclear Power Plant Unit 2 Indiana 5
05000316 AUTH. NAME AUTHOR AFFILI*TION ALEXICHiN. P.
Indiana 8c Nichigan Electric Co.
RECIP. NANE 'ECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides addi response to NRC 860924 Itr requesting schedules for addressing plant-specilic design features of AT(48 mitigation sos actuation circuitry. Requests preliminary indication of-accep tab i ltd of util program bg 870801.
DISTRIBUTION CODE:
A055D COPIES RECEIVED: LTR J ENCL J SIZE:
TITLE: QR/Licensing Submittal:
Salem ATNS Events QL-83-28 NOTES:
RECIPIENT ID CODE/NAl'1E PD3-3 LA MIQQINGTQN> D INTERNAL: ARN/DAF/LFNB NRR/DEST/ ICSB NRR/DEST/RSB NRR/DOEA/GCB f%~/'AAA'P 8
REG FILE 01 EXTERNAL:
LPDR NSIC COP 1 ES LTTR ENCL 1
0 1
1 0
1 1
0 1
0 1
1 RECIPIENT ID CODE/MANE PD3-3 PD NRR LASHER' NRR/DEBT/PSB NRR/DLPG/GAB NRR/PNAS/ILRB QGC/~HDS1 RES/DE/E IB NRC PDR COPlES LTTR ENCL 3
3 1
0 1
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1 TOTAL NUNBER QF CQPlES REGUIRED:
LTTR 20 ENCL 12
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tl f '
INDIANA8 MICHIGAN El.ECTRIC COMPANY P oO. BOX 16631 COLUMBUS, OHIO 43216 June 25, 1987 AEP:NRC:0838Z 10 CFR 50.62 Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 GENERIC LETTER 83-28, 10 CFR 50 '2, AMSAC U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Attn:
T.
E. Murley
Dear Dr. Murley:
This letter provides additional responses to your September 24, 1986 letter requesting the D.
C.
Cook schedules for addressing the plant-specific design features of the Anticipated Transients Without Scram (ATWS) Mitigation Systems Actuation Circuitry (AMSAC).
In Attachment 2 to our November 7, 1986 letter (AEP:NRC:0838V, copy enclosed in Attachment 3) we were unable to provide a complete response to several items (4, 5, 6, 8, 12, 14 and Appendix A, [a] through [d], [f] and [g])
because the responses were related to information which would be required in Technical Specifications (T/Ss).
We deferred completing these responses until the Westinghouse Owners Group (WOG) was able to resolve the issue, and if necessary, distribute to us an NRC-approved or recommended AMSAC Technical Specification.
In their letter OG-171 (dated February 10,
- 1986, copy enclosed in ) the WOG indicated that T/Ss for AMSAC are unnecessary and that plant administrative procedures would be sufficient to control AMSAC.
We concur with these statements.
Therefore, we are proceeding with our plant-specific design on the basis that no Technical Specifications are required.
In this light, we request that you disregard references to T/Ss for Items 4, 5, 6,
8, 12, and 14 in Attachment 2 to our November 7, 1986 letter.
87070>0>05 50OOSiS PDR ADOCN 0 o pDR P
0' 1
~ Dr. T. E. Murley AEP:NRC:0838Z Items 5, 6, 8, and 12 of your September 24, 1986 letter expressed concern for the control room operator human factors engineering aspect.
Our Detailed Control Room Design Review (DCRDR) program was reviewed and approved by your staff during the week of February 23, 1987. It is our intent that future control room changes or modifications, such as in this case the installation of new devices, will receive the close scrutiny of the DCRDR assessment process.
This should ensure that the human engineering properties of the control panels attained by the DCRDR Program will be maintained in the future.
With regard to Appendix A of your September 24, 1986 letter, responses to all items, a through g, are contained in Attachment 1 to this letter.
Attachment 2 to this letter is the plant-specific design we committed to provide in our November 7, 1986 letter.
Please be advised that in the attached D.
C.
Cook Plant-specific AMSAC design some Westinghouse design information is not yet available.
The original Westinghouse date for delivering the "design for the variable times to initiate AMSAC" has been delayed from the original date of April 30, 1987.
We will submit this information to you as soon as possible after we receive it from Westinghouse and have had an opportunity to review it.
We look forward to receiving preliminary indication of acceptability of the D.
C.
Cook Plant-specific AMSAC from the NRC by August 1, 1987 if possible.
This will enable us to finalize the design work and meet our scheduled implementation dates established by 10 CFR 50.62.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.
Very truly yours, i
M.
. Ale ch Vice President cm Attachments cc:
John E. Dolan (w/o attachments)
W.
G. Smith, Jr.
- Bridgman (w/o attachments)
R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis
- Region III
ATTACHMENT 1 TO AEP:NRC:0838Z RESPONSES TO NRC SAFETY EVALUATION APPENDIX A AMSAC ISOLATION DEVICE--REQUEST FOR ADDITIONAL INFORMATION
Attachment 1 to AEP:1 0838Z I ~
Page 1
NRC Safety Evaluation Appendix A Responses J
AHSAC Isolation Device Request for Additional Information NRC Request:
Please prov'de the following:
For the type of device used to accomplish electrical isolation, describe the specific testing performed to demonstrate that the device is acceptable or its application(s).
This description should include elementary diagrams when necessary to indicate the test configuration "nd how the maximum credible faults vere applied to the devices.
Response
We are presently making arrangements to have suppliers perform tests on their analog isolation devices (I/I') prior to our purchase of equipment.
We plan to require the suppliers to provide results for the test configurations listed below.
Testing will be to impose the configuration on the output side of the I/I and monitor the input circuit.
Anticipated testing circuits configurations are as follows:
1).
2).
3).
4) 5)
- nominal iC0 ohm normal an output circuit open.
an output circuit short.
a nomina'10v AC, but voltage app'ied to both both leads and ground.
a nominal 128v OC, but vo.ltage app'ed to both both leads and ground.
resistive load.
not greate=
than a
nominal 220v AC, between the output leads and between not greater than a
nominal 250v DC, between the output leads and between For items 4
6 5
above see b.
below for a discussion on applied voltage.
NRC Request:
Please provide the following:
b.
Data to ver'fy that the maximum credible faults applied during the test were the maximum voltage/current to which the device could be
- exposed, and define how the maximum voltage/current was determined.
Response
Normal design practice for D.
C.
Cook Plant categorizes cables into instrument, contro" or power cables.
These practices route each category of cable separate from the other category.
Therefore, instrument category cable would be exposed only to instrument power supply faults.
The most probable fault being a nomin~'o-load voltage of 84v DC.
However, during installation prior to circuit acceptance it is possible to impose 128v DC on the circuit through wiring errors.
Therefore the selection of the 128v DC as the
Attachment 1 to AEP:Nr
.'0838Z Page 2
maximum credible DC fault.
Additionally, the instrument power supply source voltage is 110v AC.
Although power supply source voltage feedthru is not a normally anticipated fault, this voltage is being selected as the maximum credible AC fault.
The maximum
" edible fault voltages were selected based on the above plus a
review oz the proposed design cable routings.
In performing this eview zor the proposed routing such items as signal acqu's "icn caoinet locations, AMSAC cabinet locations and the general ar a for the p'roposed cable routings were investigated.
Due to our normal design pract-'ces the imposing of control cable voltages on instrument cables is unlikely.
However to take into account the remote possibility that the P2tSAC instrument cables might be exposed to these higher voltages a survivability test is being proposed.
These voltages of nominal 220v AC and nominal 250v DC will be impo,~
d as part of the vendor testing.
These voltages will not be ter~;ed maximum credible faults but rather survival faults.
NRC Request:
Please pro"'de the ollowing:
Co Data to ver=.'y
".hat the maximum credible fault was 'applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e.,
open and short circuits).
1
Response
Figure 1 indicates that the maximum credible faults will be applied to the output o" t".e I/I in the transverse mode.
Other possible faults (open
<<;, d
-hort circuits) are also depicted.
NRC Request:
Please provide the following:
Define the pas /fail acceptance criteria for each type of device.
Response
The pass/fai!.
acceptance criteria for the proposed tests are that the I/I must pzevent the fault voltages applied in each test from damaging its input circuit or affecting its power supply circuit.
It is recognized that one or more of the proposed tests may damage the output circuit oz the I/I.
NRG Request:
Please provide the following:
e.
Provide a
commitment that the isolation devices comply with the environment qualifications (10 CFR 50.49) and with the seismic qualifications w)hach were the basis for plant licensing.
Response
The proposed location for the AfSAC I/I's is the controlled environment of the main control room for each Unit.
As such the I/I's have no env"'ronment qualification (10 CFR 50.49) requirements.
The I/I's will be purchased to comply with the seismic
Attachment 1 to AEP:N~ :0838Z Page 3
qualifications which were the basis for the plant license.
The I/I's that will be installed in existing control room cabinets will be installed in a manner which will maintain the existing cabinet rating.
Although equipment is to be purchased to our existing seismic license basis if the suppl'er provides certification to IEEE 344-1975 this certification will be used.
NRC Request:
Please provice the following:
f.
Provide a description nf the measures taken to protect the safety systems from electrical interference (i.e., Electrostatic
~~(od~
and Crosstalk) that may be generated by the ATWS circuits.
Response
The I/I's are to be enclosed in their own metal housings.
In
- addition, the circuit connecting each feedwater flow signal and turbine impulse chamber pressure signal to the AMSAC System will have an isolation device at each end.
The metal housings and connecting circuits design will protect the existing safety systems from electrica'nterference that may be generated by the ATWS circuits.
NRC Request:
Please provide the following:
g.
Provide information to verify that the Class 1E isolator is powered from a Class LE source.
Response
The AHSAC I/I's are to be installed in existing Reactor Protection System and their own control room cabinets.
These cabinets either are or are planned to be powered from one of the plant electric sources which are Class lE power sources.
Attachment 1 to AEP:: 0838Z Page 4
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ATTACHHENT 2 TO AEP:NRC:0838Z PRELIi~'lINARY 82fSAC DESIGN FOR D.
C.
COOK PLANT
Attachment 2 to A"'iNRC:0838Z
(
Page 1
This preliminary AMSAC design package is being submitted to give the NRC an opportunity to comment on the concept and circuitry to the extent that it has been finalized.
A final design package will be submitted in the final quarter of 1987 which will provide the following adai-;ional information:
(1)
More detailed location of the components.
(2)
Engineering drawings including relevant vendor information.
(5)
Exact location and numan factor attributes of the AMSAC control switches and annunciators in the Control Room.
(4)
Recommended t st/surveillance.
The design bases for the design have already been submitted to the NRC by Nestinghouse.
The issue of isolators and their qualification is described in attachment 1
(Response to Appendix A of the Safety Evaluation Report).
Our AMSAC design is the low feedwater flow option.
We will trip the turbine and initiate auxiliary feed water flow when we have less than 25K. feed flow to 5 out of 4 steam generators and we are above 40! power.
These setpoints nave been given to us by Westinghouse.
Figure g1 shows tne signal sensing block diagrams.
We will sense feedwater flow from the existing flow transmitters (FFC-211,
- 221, 251, 241).
The AMSAC power permissive signal will be sensed from the existing turbine 1st stage pressure transmitters (NPC-253, 254).
We are adding new current repeaters (I/I) to each sensing loop.
For the feed flow sensing
- loops, we will be placing the l/I's in the RPS cabinets and powering them from the existing power supolies:
The Control Room Instrumentation Distribution System (CRIDS).
These 120V ac supplies are powered from the existing station batteries via Class 1E inverters.
Test points are available to inject signals for testing, trouble shooting, and maintenance.
The logic equipment is the Foxboro Spec.
200.
It will be powered from the ANSAC inverter and will be housed in the AMSAC cabinet which will be located in the control room.
Figure
<f2 contains the elementary logic diagram.
The dc source is our Class 1E iJ-Train battery which powers the aux.
feedwater valves.
The i3 Train battery is independent of the station batteries.
The 250V iJ-Train Battery will be isolated from AMSAC through qualified 1E fuses.
The ANSAC inverter will provide all of the logic power (120 VAC).
The undervoltage relay (27AMUV) will annunciate in the control room when ANSAC control bus voltage is unavailable.
The contacts from the flow output relay
Accacnment 2 to aeP:NRC:Oa5dZ Page 2
cards are arranged to start the initiate timer (62 ANIN) if we get low feedwater to any 5 out of 4 loops.
The initiate timer is shown to have tne time delay setting of 25 seconds.
We will address the variable timer issue (which is being developed by Westinghouse) when ve have received all of the technical data from the Westinghouse Owner's Group.
The output relay contacts from the turbine 1s"; stage pressure are in an "and" configuration.
'~;e can test the power permissive by placing control swi tch 101CS-1 in bypass/test.
Please note that Ai~lSAC will "go to completion" once we receive an initial signal even though the reactor power drops belov 40$ power subsequently.
Once AHSAC has gone to completion, the circuit will seal itself in (IR-2 (SI)) ana muss be a"knowledged through a manual reset (control switch "iv1CS-5I.
Provisions have been made to manually initiate AiISAC throu:h two spring return control switches (101CS-5, 101CS-4) when A"iSAC is placed in bypass/test, the initiating relays (I..-1, 2, z) vill be disabled and a test relay (ATR) will be enabl d.
This will allow us,to test the ANSAC logic without testing tne AHSAC output relays.
(ie. without initiating turbine trip and aux. feedwater flow). If the test relay is oicked up, ir. will indicate a successful test and seal itself in (ATR(Si)).
The signal can be cleared through control switch 101CS-2 (manual test reset).
Once ANSAC has been restored to its normal state (161C>-1 in "normal" ), the test indication will verify that the contacts have closed.
Ai~1SAC will be declared inoperabl
=- dur ing tescing.
Figure e5 shows the contact developments for the AiMSAC logic and output relays.
Rel. ys
- TR1, IR2, IRAN will, when energized, initiate the auxiliary feedwater system and tr ip the main tur bine.
Figure P4 contains she switches, indicating lights, and annunciator drops vnich vill oe placed in the control room.
The exact panel locations vill oe finalized after the Detail Control Room Design Reviev.
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Attachment 2 to AEP:NRC:0838Z AMERICANELECTRIC POWER SERVICE CORP.
1 RIVERSIDE PLAZA COLUMBUS, OHIO OAT~ ~>>
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ATTACHMENT 3 TO AEP:NRC:0838Z LETTER, L.
D.
BUTTERFTELD TO H.
R.
- DENTON, FEBRUARY 10, 1986
- LETTER, M.
P.
ALEXICH TO H.
R.
- DENTON, NOVEMBER 7, 1986