ML17319B156
| ML17319B156 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/22/1982 |
| From: | Hering R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17319B157 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 AEP:NRC:00591, AEP:NRC:591, NUDOCS 8201290311 | |
| Download: ML17319B156 (10) | |
Text
~ r REGULATORY ORMAT ION DISTRIBUTION "SYS (RIDS)
'AGCBSSION NBR 8201290311,,DOC
~ DATE:.82/Oi/22 NOTARIZED:
NO DOCKET FACIL:50-315 Dona 1 d, C.
Cook Nuc l ear Power Plan~,
Uni~t 1, Indiana 8
05000315 50 316 Donald C ~
Cook Nuclear Power Plantr "Uni,t 2r Indiana 8
05000316
'AUTH BYNAME AUTHOR AFFILIATION MERINGiR ~ F ~
Indiana 8 Michigan Electr ic Co,
~RBC IP. NAME RECIPIENT AFFILIATION DENTONEH ~ RE Office of Nuclear Reactor Regulationi Director
SUBJECT:
Requests changes rto Tech Specsiconsisting of vevised pages
.,to App A.Descrip'tion of changes encl',
DISTRIBUTION CODE:
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TITLE: Response to NUREG
~ 0737/NUREG-0660 TMI Action.Plan Rgojts (OL's)
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INDIANA IIt MICHIGAN ELECTRIC COMPANY P. O.
BOX 18 BO WLING G R E EN STATION NEW YORK, N. Y. 10004 January 22, 1982 AEP:NRC:00591 Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 TECHNICAL SPECIFICATIONS CHANGE REQUEST REQQPEg 9-JAN g 8 )geZ 12 II'4IIQIIIgfINIIg fggf I0v~~~F Nr..Harold R. Denton, Director Office of Nuclear Reactor Regulation U.
S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Nr. Denton:
This letter and its Attachments request several changes to the Donald C.
Cook Nuclear Plant, Unit Nos.
1 and 2 Appendix A Technical Specifications.
Attachment No.
1 to this letter contains the description of the changes.
Attachment No.
2 contains the revised Technical Specific-ation pages for Unit No.
1 and Attachment No.
3 contains the revised Technical Specification pages for Unit No. 2.
All changes are indicated by a vertical line on the right-hand side of the page in Attachment Nos.
2 and 3.
The proposed Technical Specification changes contained herein have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC) and by the AEPSC Nuclear Safety and Design Review Committee (NSDRC).
Four proposed Technical Specification revisions are contained in this submittal.
Change Nos.
1, 2, and 3 are considered to be Class II amendments
($1,200 fee each).
Class I duplicate fees also apply for these changes.
The payment for Change No.
4 will be made as part of the fee to be levied for the issuance of the Category B Technical Specifications of NUREG-0737.
- Enclosed, therefore, is a check in the amount of $4,800.00 for NRC processing of the aforementioned requests.
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Nr...Harold R. Denton AEP: NRC: 00591 This document has been prepared following Corporate procedures which incorporate a'easonable set of controls to insure its accuracy and com-pleteness prior to signature by the undersigned.
Very truly yours, RFH/os R. F. Hering Vice President cc:
John E. Dolan - Columbus R.
W. Jurgensen W. G. Smith - Bridgman R.
C. Callen G. Charnoff Joe Williams, Jr.
NRC Resident Inspector at Cook Plant - Bridgman R.
S. Hunter
ATTACHMENT NO.
1 TO AEP:NRC:0591 DESCRIPTION OF PROPOSED TECHNICAL SPECIFICATION CHANGES FOR D. C.
COOK UNIT NOS.
1 AND 2
~
P
Unit l; Page 3/4 3-12; 'Section 3.3.1.1 Unit 2; Page 3/4 3-11; Section 3.3.1.1 For Unit Nos.
1 and 2, it is requested that'urveillance requirements for the "Source Range;- Neutron Flux" Channels be deleted in Mode 2.
The Source Range Channels do not provide any useful information in Mode 2.
Furthermore, Westinghouse Technical Bulletin NSD-TB-80-8 recommended not powering Source Range detectors while at power because of possible detector degradation or failure.
For Unit 2, it is additionally requested that surveillance requirements for the "Source
- Range, Neutron Flux" Channels be deleted in Mode 6.
While in Mode 6, a weekly surveillance is already required under Specification 4.9.2.
For Unit 2, it is also requested to delete the "M" requirement of the Channel Functional Test for the "Source
- Range, Neutron Flux" Channels and to change the Channel Calibration requirements of" the
'Intermediate and Source
- Range, Neutron Flux" Channels (Item Nos.
5
~ and 6 in Table 4.3-1) to "N.A." (not applicable).
The monthly Functional Test
("M") is unnecessary as such testing performs no useful function.
The deletion of the monthly requirement will make Table 4.3-1 of Unit 2 consistent with that -of Unit.1..
- Further, under note (6) of Table 4.3-1, neutron detectors may be excluded from Channel Calibration.
These changes will not adversely affect the health"and safety of the general public.
Chan e No.
2 Unit 1; Page 3/4 3-26a; Section 3.3.2.1 Unit 2; Page 3/4 3-25a; Section 3.3.2.1
Reference:
AEP:NRC:0268 Presently, the Loss-of-Voltage relays in paragraphs 6b and 8a in both Units 1
and 2
are specified as
- 3196,
+
18 volts and the Degraded Grid Voltage relays in paragraph 8b are specified as
- 3596,
+18 volts.
The Technical Specification values for these voltages and their associated tolerance bands are extremely conservative.
Attempts to comply with the allowable voltage values in the Technical Specifications have been unsuccessful due to the inability of the relays to repeat their settings within the desired tolerance.
It is thus proposed to change the allowable values for Loss-of-Voltage relays in paragraphs 6b and 8a of both Units from 3196+18 volts to 3196,+18,
-36 volts and change the allowable values of the Degraded Grid Voltage relays in paragraph 8b of both Units from 3596+18 volts to 3596, +36,-18 volts.
Currently, the Loss-of-Voltage relays have Technical Specification allowable values between 79.45%
and 80.35% of the rated voltage value (4kV).
The proposed change would alter the range from 79.00% to 80.35%
(3196, +18, -36 volts).
This change is acceptable since motor operation at 79.00% of rated voltage for two-minutes is not significantly different from motor operation at 79.45% of rated voltage for the same two-minute period.
~ l
The Degraded Grid Voltage relays now have Technical Specification allowable values between 89.45%
and 90.35% of the rated voltage value (4kV)'.'Throposed change would alter the range from 89.45% to 90.80%
(3596, +36, -18 volts).
This change is acceptable since under postulated worst case"Degraded Grid Voltage conditions, the voltage would recover to 93.3% of rated voltage which is still above this proposed new upper tolerance value.
These proposed changes are consistent with our analysis for loss of Voltage and Degraded Grid Voltage events and will not affect the health and safety of the general public.
Chan e No.
3 Unit 1; Page 3/4 2-14;.Section 3.2.5
'Unit 2; Page 3/4 2-16; Section 3.2.5
- ~
This change revises the footnote of Table 3.2-1.
A request for this footnote to be revised was previously submitted on December 22, 1978 in AEP:NRC:0109 (Unit 1) and on February 13, 1979 in AEP:NRC:
0111 (Unit 2).
The change requested therein was further modified during discussions with members of your'Staff. It was agreed that the footnote would be modified to reflect the wording of the Standard Technical Specifications contained in Revision 3
of NUREG-0452.
Recent discussions with members of your Staff indicate that this modified footnote of Table 3.2-1 will be issued shortly.
The present change further modifies the footnote to make the reporting requirements of Specification 6.9.1.9 not applicable for transients during start-up or shutdown operations.
It is requested that this present change be processed independently of our previous request contained in AEP:NRC:0109 and AEP:NRC:0111 as modified through discussions with members of your Staff.
The attached Technical Specification changes in Attachment Nos.
2 and 3 reflect both the original change request, as modified through discussions with members of your Staff, and the present change request.
These proposed changes will not adversely affect the health and safety of the general public.
Chan e No.
4 Unit 1; Page 3/4 6-17; Section 3.6.3 Unit 2; Page 3/4 6-18; Section 3.6.3 In order to meet the requirements of NUREG 0737, II.B.3, Post-Accident Sampling Capability, six new containment isolation valves are being installed per Unit.
These include sump
- sample, containment gas
- sample, and waste return valves.
Table 3.6-1 of both Unit's Technical Specifications has been changed'o reflect the addi,tion of these. valves.
This Technical Specification change will become applicable when the valves are installed.
The new valves are numbered 47-52.
The valve numbers in Table 3.6-1 have been changed to reflect the addition of these six valves.
This change will not affect the health and safety of the general public.