ML17331A596
| ML17331A596 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/23/1981 |
| From: | Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.E.1.2, TASK-TM AEP:NRC:00307F, AEP:NRC:307F, NUDOCS 8101300494 | |
| Download: ML17331A596 (5) | |
Text
REGULATORY
- ORHATION DISTRIBUTION SYS l:
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ACCESSION NBRS 8101300494,OOC
~ DATE s 81/01/23 NOTARIZED; FACILs5 onald CD Cook Nuclear Power Plantr Unit 1r 0
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INDIANA Ik MICHIGAN ELECTRIC COMPANY P. O.
BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 January 23, 1981 AEP:NRC:00307F Donald C.
Cook Nuclear Plant Units 1
8 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 Auxiliary Feedwater System Automatic Initiation and Flow Indication Hr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
This letter transmits two (2) revised
- pages, correcting errors of an administrative nature, in the attachment to our letter dated December 10, 1980 (AEP:NRC:00307E).
The revisions are indicated by bars on the right hand margin and have been discussed with members of your staff.
The revised pages should be inserted into the attachment to our AEP:NRC:00307E submittal, replacing the corresponding pages which are to be discarded.
On page 1 of the attachment to AEP:NRC:00307E, item B.iv), the words in brackets "(either Unit)" have been deleted since this was inadvertently carried over from the time when the operation of the motor driven auxiliary feedwater pumps was shared by both Units.
The motor driven pumps do start automatically from the initiation signals within their own Unit.
On page 2, in the response to item 2,. the last sentence has been revised to correctly indicate that the BOP inverter is an emergency load for the surveillance testing of the safety-related station battery per Table 4.8-1 of our Technical Specifications.
Operability of the safety related station batteries is required by the Technical Specifications and
. not of'.the BOP, inverter as the original sentence might have implied.
]CHOO/
Mr. Harold R. Denton, Director AEP:NRC:00307F
~ We hope that this has not caused any inconvenience in your staff's review efforts on this matter.
Very truly yours, S.
unter Vice President cc:
R.
C. Callen G. Charnoff John E. Dolan R.
W. Jurgensen D. V. Shaller - Bridgman Region III Resident Inspector at Cook Plant - Bndgman
ATTACHMENT TO AEP:NRC:0307E These responses are in the. same format as the enclosure to Mr. S. A; Varga's October 31, 1980 letter.
Response
To Item 1:
The operating bypasses associated with 4he automatic initiation logic are as follows:
A.
Turbine Driven Auxiliar Feedwater Pum TDAFP):
There are no bypasses in the TDAFP logic'.which prevent automatic initiation.
B.
Motor Driven Auxiliat Feedwater Pum s
MDAFP):
The MDAFP's are automatically started by:
i) low-low steam generator water level in any one of the four steam generators, ii) undervoltage of RCP bus (2(4 logic),
iii) any safety injection actuation.signal derived from:
a ~
d.
e.
pressurizer pressure
- low, differential pressure between steam lines - high, steam flow in two steam lines - high concident with either '.Tavg-low-low or coincident with steam line pressure-low (Unit 1 only),
steam line pressur e - low.(Unit 2 only),
containment pressure
- high, and manual-iv) blackout safeguards sequence v) loss of main fee'dwater pumps
There are two (2) bypasses in the HDAFP automatic initiation logic:
1.
The P-11 interlock in the Reactor Protection System (RPS) logic is used to allow the manual block of the safety injection actuation signal generated from pressurizer pressure-low.
This interlock is reset automatically when pressurizer pressure goes above 1915 psig for Unit 1 and 2010 psig for Unit 2.
2.
The P-12 interlock in the RPS logic is used to allow the manual block of the safety injection actuation signal generated from; (a) steam flow in two steam lines-high coincident with steam line pressure-low, in Unit 1
and (b) steam line pressure-low, in Unit 2.
This interlock (both Units.) is reset automatically
>>hen 'primary system temperature is above the Tavg-low-low setpoints of 541oF.
The remaining signals which generate a safety injection actuation (which in turn automatically initiates the HDAFP starting) and the other automatic HDAFP start signals listed above do not have bypasses in the auxiliary feedwater initiation logic.
Res onse To Item 2:
The auxiliary feedwater flow indicators, FFI-210, FFI-220, FFI-230 and FFI-240.are fed from the balance-of-plant inverter in each unit (non-class IE).
This is an uninterruptable power source which is fed from the CD battery of Unit 1 and the AB battery of Unit 2 (safety related station battery).
One instrument channel per steam generator is provided.
The flow indication instruments are located on Panel SG in the. main control room and on the appropriate hot shutdown panel for each unit.
Also, each pump'has a
discharge pressure indicator in the control room, f'PI-244, FPI-253, FPI-254.
The pressure indicators are powered from the same source as the flow in-dicators (FFI's).
The BOP inverter is an emergency load for the safety' related station battery per the surveillance requirements of Techni,cal Res onse. To Item 3:
The steam generator level measurement systems are all supplied from the vital instrument buses which are -Class IE uninterruptable power sources.
There are 4 independent vital instrument
- buses, Channels 1, 2, 3
and 4.
below:
The level instrumentation for the Steam Generators is tabulated A.
Steam Generator Ho.
1 BLP-110, Channel 4 Indicator BLP-111, Channel 2 Indicator-Recorder