ML17334B014
| ML17334B014 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/08/1986 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17334B015 | List: |
| References | |
| AEP:NRC:0956C, AEP:NRC:956C, NUDOCS 8612120318 | |
| Download: ML17334B014 (11) | |
Text
REGULATORY FORNATION DISTRIBUTION SY N (RIDS)
%.s ACCESSION NBR: 8612120318 DOC. DATE: 86/12/08 NOTARIZED:
NO D CKET FACIL: 56-315 Donald C.
Cook Nuclear Power Plant>
Unit 1> Indiana 5
05 00315 50-316 Donald C.
Cook Nuclear Power Plant>
Unit 2>
Ind iana 5
050 316 AUTH. NAl'lE AUTHOR AFFILIATION ALEXICH>l'1. P.
Indiana 8c Nichigan Electric Co.
RECIP. NAl1E RECIPIENT AFFILIATION DENTON> H. R.
Office of Nuclear Reactor Regulation.
Director <post 851125
SUBJECT:
Application for amend to Licenses DPR-58 8c DPR-74, revising Tech Specs to reflect replacement of liquid radwaste effluent 1 inc moni tor. Fee pa id.
DISTRIBUTION CODE:
A001D COPIES RECEIVED: LTR ENCL SIZE:
TITLE:
OR Submittal:
General Distribution NOTES:
RECIPIENT ID CODE/NAl'lE PWR-A EB PWR-A FOB PWR-A PD4 PD 01 PWR-A PSB INTERNAL: ADN/LFNB RR/
TSCB Q FILE 04 COPIES LTTR ENCL 1
1 1
1 5
5 1
1 0
1 1
RECIPIENT ID CODE/MANE PWR-A EICSB PWR-A PD4 LA WIGGINGTON> D PWR-A RSB ELD/HQS3 NRR/ORAS RQN3 COPIES LTTR ENCL 2
2 1
0 1
1 1
1 1
0 0
1 EXTERNAL:
EQRcQ BRUSQUE> S NRC PDR 02 LPDR NSIC 03 05 2
2 TOTAL NUNBER OF COPIES REQUIRED:
LTTR 24 ENCL 20
t K
II L
'I II I
INDIANA8 MICHIGAN ELECTRIC COMPANY P.O, BOX 16631 COLUMBUS, OHIO 43216 Decembei 8,
1986 AEP:NRC:0956C Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION TECHNICAL SPECIFICATIONS CHANGE REQUEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
This letter and its attachments constitute an application for amendment to the Technical Specifications (T/Ss) for the Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2.
Specifically, we are proposing a change to T/S 3.3.3.9, Table 3.3-12, to reflect the replacement of the liquid radwaste effluent line monitor.
The reasons for the proposed change and our analysis concerning significant hazards considerations are contained in Attachment.
1 to this letter.
The proposed revised Technical Specification pages are contained in.
We believe that the proposed change 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 (PNSRC) and will be reviewed by the Nuclear Safety and Design Review Committee (NSDRC) at their next regularly scheduled meeting.
In compliance with the requirements of 10 CFR 50.91(b)(1),
copies of
~ this letter and its attachments have been transmitted to Mr. R.
C. Callen of the Michigan Public Service Commission and Mr. G. 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.
8612120318 861208 'I PDR ADOCK 05000315 PDR
1 r
C r V J
'r. Harold R. Denton 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 M. P.
A exich jgj@
Vice President 0'm Attachments cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G'. Bruchmann G. Charnoff NRC Resident Inspector
- Bridgman
I
ATTACHMENT 1 TO AEP:NRC:0956C
'EASONS AND 10 CFR 50.92 ANALYSIS FOR CHANGE TO THE DONALD C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 TECHNICAL SPECIFICATIONS
I
'to AEP:NRC:0956C Page 1
The purpose of this proposed change is to allow the replacement of the liquid radwaste effluent line monitor.
The current monitor, referred to as 1-R-18 in the Unit 1 T/S and 2-R-18 in the Unit 2 T/S, is being replaced by a new monitor, 12-RRS-1001.
This change in instrument number should be reflected in T/S Table 3.3-12, Item l.a.
We committed to replace this monitor in our response to Inspection Report Nos.
50-315/85-06 and 50-316/85-06 by the end of 1986.
While the
.physical installation of the new monitor is scheduled to be completed by the end of 1986, the monitor will not be capable of meeting all T/S requirements until all post-installation calibration and testing is completed.
Therefore we request that a footnote be added to allow the existing monitor (1-R-18/2-R-18) to fulfillthe T/S requirements until the new monitor is declared OPERABLE.
In our submittal AEP:NRC:0956A (dated January 21, 1986 and issued as Amendment 94 for Unit 1 and Amendment 80 for Unit 2),
we added the instrument numbers to the radiological monitoring system.
The addition of the instrument numbers was an editorial change to identify to the operators exactly what instrumentation was required by T/Ss.,
A change of one of these instrument numbers is clearly editorial and thus administrative in nature.
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 possib'ity of a new or different kind of accident from any accident previously analyzed or evaluated, or (3) involve a significant reduction in a margin or safety.
Criterion 1 The proposed change is administrative in nature since it only updates the instrument number listed in the T/Ss to reflect the replacement of the liquid radwaste effluent line monitor.
This change does not impact the systems involved except that the new monitor cannot be used to fulfillthe T/S requirements until this T/S change is issued.
Therefore, we believe this change does not involve a significant increase in the probability or consequences of a previously analyzed accident.
Criterion 2
This change is purely administrative in nature.
It is representative of a monitor change which resulted from a commitment to NRC Region III and is considered an enhancement.
Therefore we believe this change will not create the possibility of a new or different kind of accident than has previously been analyzed or evaluated.
Attachment 1 to AEP:NRC:0956C Page 2
Criterion 3
Since this change is administrative in nature, it will not impact the ability of plant systems and components to perform their safety function.
Therefore we believe this change will not involve a significant reduction in a margin of safety.
The Commission has provided guidance concerning the determination of significant hazards by providing certain examples (48 FR 14780) of amendments considered not likely to involve significant hazards considerations.
The first example is that of a purely administrative change to the T/Ss:
for
- example, a change to achieve consistency throughout the T/Ss, correction of an error, or a change in nomenclature.
We believe that the change requested in this letter is of the type specified in the example.
Since this change is administrative in nature, it does not reduce a margin of safety, does not increase the probability or consequences of a previously analyzed accident, and does not introduce the possibility of a new accident.
Therefore, we believe this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.
ATTACHMENT 2 TO AEP:NRC:0956C REVISED PAGES FOR THE DONALD C.
COOK NUCLEAR PLANT UNIT NOS.
1 AND 2 TECHNICAL SPECIFICATIONS