ML17326B432
| ML17326B432 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/31/1988 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML17326B433 | List: |
| References | |
| AEP:NRC:0916AL, AEP:NRC:916AL, NUDOCS 8809070507 | |
| Download: ML17326B432 (7) | |
Text
ACCESSION NBR:8809070507 DOC.DATE: 88/08/31 NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana 05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana 05000316 AUTH.NAME AUTHOR AFFILIATION ALEXICH,M.P.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E.
Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-58
& DPR-74,revising submittal of 870326.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT ID CODE/NAME PD3-1 LA STANG,J COPIES LTTR ENCL 1
0 1
1 RECIPIENT'D CODE/NAME PD3-1 PD COPIES LTTR ENCL 5
5 INTERNAL: ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 NUDOCS-ABSTRACT EG E
01 EXTERNAL: LPDR NSIC 1
0 1
1 1
1 1
1 1
1 1
1 1
1 1
1 NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 OGC/HDS1 RES/DSIR/EIB NRC PDR 1
1 1
1 1
1 1
1 1
0 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 22 ENCL 19
Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC'0916AL Donald C.
Cook Nuclear Plant Units 1 and 2
License Nos.
50-315 and 50-316 Docket Nos.
DPR-58 and DPR-74 CHANGES TO TECHNICAL SPECIFICATION CHANGE SUBMITTAL OF MARCH 26, 1987 (AEP:NRC:0916W)
U.
S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Attn:
T. E. Murley August 31, 1988
Dear Dr. Murley:
Pursuant to a request by your staff on August 9, 1988, attached are Technical Specification (T/S) pages that revise our submittal of March 26, 1987 (AEP:NRC:0916W).
The changes are consistent with your staff's request, and in all circumstances are more restrictive than our previous request or are administra-tive in nature.
Therefore, we believe the revisions do not require notification in the Federal Register per 10 CFR 50.91.
The changes are described below.
1)
Pa es 3 4 3-9 Unit 1 and 3 4 3-8 Unit 2 The NRC staff requested that the description of the P-7 and P-8 interlock in Table 3.3-1 be revised to provide greater detail on the interlock functions.
The logic for reactor trip on low flow in any loop can be actuated by either of two signals.
These are (1) two of three loop low flow indications and (2) loop reactor coolant pump (RCP) breaker position open.
The output of the "OR" logic of these two signals is input to the loop logic, one of four loops indicating low flow above P-8 and two of four loops indicating low flow below P-8 and above P-7.
In principle, a trip below P-8 and above P-7 could result from an RCP breaker open in one loop and two of three low flow indications in a different loop.
The interlock descriptions were revised to reflect the fact that RCP breaker and loop low flow are treated as equivalent indications of low flow.
This change is purely administrative in nature, intended only to clarify the T/S description of the existing P-7 and P-8interlocks'oa 8809070507 88083i PDR ADOCK 05000315 e
, ~I
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Dr. T. E. Murley AEP:NRC:0916AL The changes described above were unrelated to our original AEP:NRC:0916W request, which proposed to conservatively change the Unit 1 P-8 setpoint from greater than or equal to 51$ of rated thermal power to greater than or equal to 31% of rated thermal power, to achieve consistency with the Unit 2 T/S.
No changes to the corresponding Unit 2 page were requested in AEP:NRC:0916W.
However, since the staff's comment was equally applicable to the Unit 2 T/S, we have included the change for both unit's T/Ss in the attachment to this letter.
2)
Pa es 3 4 3-12 14 Unit 1 and 3 4 3-11 13 Unit 2 AEP:NRC:0916W proposed to add T/S 4.0.4 exemptions for the channel calibrations and channel functional tests for the Unit 1 source
- range, neutron flux reactor trip (Table 4.3-1 Functional Unit 6).
Identical changes had been granted for the Unit 2 source range surveillances in Amendment 82, dated May 21, 1986.
The surveillances are required, per T/S Table 4.3-1, to be current in Modes 2, 3, 4, and 5 (below the P-6 setpoint).
The exemption for the 18-month channel calibration was proposed to address the situation in which the calibration may expire before the reactor leaves Mode 1 and enters Mode 2, since the calibration cannot be performed in its entirety in Mode 1
~
Similarly, the T/S 4.0.4 exemption for the monthly channel functional test was proposed to address the situation that results from a reactor trip after continuous power operation of more than 31 days.
The surveillance cannot be performed at power without damaging the source range detectors.
Rather than grant a 4.0.4 exemption for Unit 1 that would be applicable regardless of what modes the reactor had been in prior to mode changes, the NRC staff requested us to modify our proposed exemption to require that the surveillances be completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after leaving Mode 1.
This change, which is more restrictive than our original request, has been incorporated into the pages found in the attachment to this letter.
Because the NRC staff's request was equally applicable to the Unit 2 T/Ss, we have also included the revised T/S 4.0 '
conditions for the Unit 2 T/Ss in the attachment to this letter.
10 CFR 50.92 Evaluation As discussed previously, the changes proposed in this submittal are either more restrictive than previously proposed in our letter AEP:NRC:0916W, or are administrative in nature.
- Thus, the
~
J
Dr. T. E. Murley
-3 AEP:NRC:0916AL conclusions of the 10 CFR 50.92 evaluation submitted in AEP:NRC:0916W remain valid, and therefore the modified changes should not 1) involve a significant increase in the probability or consequences of a previously analyzed accident,
- 2) create the possibility of a new or different kind of accident from any previously analyzed or evaluated, or 3) involve a significant reduction in a margin of safety.
Other Licensin Issues A check in the amount of $150.00 was enclosed with our original submittal (AEP:NRC:0916W).
Because this submittal only modifies the original submittal, at the NRC staff's request, we believe no additional fees per 10 CFR 170.12 are required.
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.
. Ale ich Vice President ldp Attachments cc:
D. H. Williams, Jr.
W.
G. Smith, Jr.
- Bridgman G. Bruchmann R.
C. Callen G. Charnoff NRC Resident Inspector
- Bridgman A. B. Davis
- Region III
Attachment to AEP:NRC:0916AL Revised Technical SpeciEication Pages