ML17325B095
| ML17325B095 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/12/1989 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML17325B096 | List: |
| References | |
| AEP:NRC:1030A, NUDOCS 8901180309 | |
| Download: ML17325B095 (10) | |
Text
- 'l ACCELERATED DISglBUTION DEMONSTRgWOAI SYSTEM
.REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS).
ACCESSION'NBR:8901180309 DOC.DATE: 89/01/12 NOTARIZED: NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 6
05000315 50-316 Donald C.
Cook Nuclear. Power Plant, Unit 2, Indiana 6
05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana S Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-58
& DPR-74,modifying Tech Spec Table 3.3-3.Fee paid.
DISTRIBUTION CODE:
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SIZE: F 3
TITLE: OR Submittal:
General Distribution NOTES:
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TO XZZMZMXE YOUR NAME FMH DISTBIKITIGN LISTS FOR DOCtIMENZS YOU DOlNiT NEED<m TOTAL NUMBER OF COPIES REQUIRED:
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Indiana Michigan Power Company P.O. Box 16631 Columbus, OH 43216 INlMANA PllCNIGQN PUÃPlR AEP:NRC:1030A Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 TECHNICAL SPECIFICATION CHANGE:
MOTOR-DRIVEN AUXILIARYFEEDWATER ACTUATION SIGNALS U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 Attn:
T.
E. Murley January 12, 1989
Dear Dr. Murley:
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2.
Specifically, we are proposing to modify T/S Table 3.3-3 (Engineered Safety Features Actuation System Instrumentation) so that it more accurately reflects the actuation signals for the auxiliary feedwater system.
We believe that the proposed changes will not result in (1) a significant change in the types of effluents or a significant increase in the amounts of any effluent that may be released offsite, or (2) a significant increase in individual or cumulative occupational radiation exposure.
These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and will be reviewed by the Nuclear Safety and Design Review Committee at their next regularly scheduled meeting.
In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to Mr. R.
C. Callen of the Michigan Public Service Commission and Mr. George Bruchmann of the Michigan Department of Public Health.
Pursuant to 10 CFR 170.12(c),
we have enclosed an application fee of $150.00 for the proposed amendments.
89'01 180309 8%0112 PDR ADOCK 050003i5 P
T.
E. Murley AEP:NRC:1030A This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely, M. P. Ale ich Vice President eh Attachments cc:
D.
H. Williams, Jr.
W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis
- Region III
Attachment 1 to AEP:NRC:1030A Reasons and 10 CFR 50.92 Analyses for Changes to the Donald C.
Cook Nuclear Plant Units 1 and 2 Technical Specifications
Attachment 1 for AEP:NRC:1030A Page 1
This letter proposes modifications to Technical Specification (T/S) Table 3.3-3, Functional Unit 6.b.
This functional unit involves the motor driven auxiliary feedwater pump start on a 4kv bus loss of voltage signal.
The modifications we are proposing are intended to clarify the T/S such that it more accurately reflects the number of channels present and the number'of channels necessary to provide the motor driven auxiliary feedwater function.
Descri tion of S stems A schematic drawing of the motor driven auxiliary feedwater pump system at the Cook Nuclear Plant is presented in Figure 1 of this attachment.
As indicated in the figure, the Train A (East) pump delivers flow to Steam Generator No.
2 via motor operated valve FM0-222, and to steam generator No.
3 via FMO-232.
Likewise, the Train B (West) pump delivers flow to steam generator No.
1 via FM0-212, and to steam generator No. 4 via FM0-242.
A schematic drawing of the electrical bus arrangement with regard to the motor driven auxiliary feedwater pumps and their associated motor operated valves is provided as Figure 2.
As indicated in the figure, the Train B pump is powered from the 4kv bus T11A.
The valves associated with the Train B pump are powered from the 600-volt bus 11A, which is fed from bus T11A.
The Train A pump and valves are similarly fed from 4kv bus TllD and 600-volt bus 11D, respectively.
There are 3 relays (channels) which indicate loss of voltage on each of the 4 safety busses.
Actuation of 2 of the relays on bus TllAwill start an emergency diesel generator and the Train B motor driven auxiliary feedwater pump.
Similarly, actuation of 2 of the relays on bus TllD will start an emergency diesel generator and the Train A pumps The FMO valves associated with the motor driven auxiliary feedwater pumps are normally open.
Should they be closed, for testing purposes, loss of voltage will cause both trains of valves to be opened (after starting the diesel generator) provided voltage is lost to both safety busses associated with a train. For
- example, actuation of 2 of 3 relays on bus TllA and 2 of 3 relays on bus TllB will open valves FM0-212,
-222,
-232, and -242.
Should the pumps start without the valves opening, the pumps are protected from dead-heading by an emergency leak-off (recirculation) line to the condensate storage tank.
Reason for Chan e
T/S Table 3.3-3 Functional Unit 6.b as currently written states that there are a total of 2 channels per bus, with both channels
Attachment 1 for AEP:NRC:1030A Page 2
per bus required to trip.
The functional unit as written is incorrect since, as described
- above, there are actually 3 channels per bus.
Furthermore, it is misleading in that it does not indicate that loss of voltage on two busses is necessary to open the FMO valves.
For these
- reasons, we are proposing to modify the functional unit as indicated below.
Functional Unit Total No. of Channels Channels to Tri
- b. 4kv Bus loss of voltage 3/bus Pump start 2/bus (T11A-Train B; T11D-Train A)
Valve Actuation (Both trains) 2/bus on (T11A 6 T11B or 2 busses T11C 6 T11D)
These changes are considered to be administrative in nature.
They are intended to clarify the T/Ss with regard to actuation of motor driven auxiliary feedwater.
No operability or surveillance requirements will be reduced as a result of this change.
10 CFR 50.92 Criteria Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously analyzed or evaluated, or (3) involve a significant reduction in a margin of safety.
Criterion 1 These changes are intended only to clarify and correct the existing T/S so that it more accurately reflects the actuation signal for motor driven auxiliary feedwater flow in the event of a loss of voltage on the safety busses.
No operability or
Attachment 1 for AEP:NRC:1030A Page 3
surveillance requirements have been reduced.
Therefore, we believe the change does not involve a significant increase in the probability or consequences of an accident previously analyzed, nor does it involve a significant reduction in a margin of safety.
Criterion 2 The change does not involve physical modifications to the plant or changes in plant operation.
Therefore, the change should not create'he possibility of a new or different kind of accident from any pieviously analyzed or evaluated.
Criterion 3
See Criterion 1, above'astly, we note that the commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14870) of amendments considered not likely to involve significant hazards consideration.
The first of these examples refers to changes which are purely administrative in nature:
for example, changes to achieve consistency throughout the T/Ss, correction of errors, or changes in nomenclature.
The proposed change only clarifies the present T/S and corrects errors in the present text.
We are not proposing to reduce any present requirements.
For these
- reasons, we believe that the example cited is applicable and that the proposed change should not involve significant hazards consideration.
STEAM GENERATOR NO. 4 STEAM GENERATOR NO. 3 STEAM GENERATOR NO.
1 STEAM GENERATOR NO. 2 FMO 242 M
FMO 212 M
FMO 231 M
FMO 221 M
FMO 222 M
FMO 232 EMERGENCY LEAK-OFF TO CONDENSATE STORAGE TANK EMERGENCY LEAK-OFF TO CONDENSATE STORAGE TANK EMERGENCY LEAK-OFF TO CONDENSATE STORAGE TANK WEST MOTOR DRIVEN A.F.P.
CONDENSATE STORAGE TANK TRAIN B
TURBINE DRIVEN A.F.P.
N TRAIN DC CONTROL POWER EAST MOTOR DRIVEN A.F.P.
TRAIN A
Figure 1
Donald C. Cook Nuclear Plant auxiliary feedwater system
T11A 4KV BUSSES T118 T11C T11D MOTOR DRIVEN AFW PtHHP TRAINB DIESEL GEN.
1AB DIESEL GEN.
1CD MOTOR DRIVEN AFW PUMP TRAINA TRANSFORMER 11A TRANSFORMER 11D 800V BUS 11A 600V BUS 11D VALVES FMO 212 8 242 VALVES FMO 222 8.
232 TRAIN 8 TRAIN A')lure 2 Porter sources for motor driven auxiliary feedveater pumps and associated valves
ft