ML17334A851

Application for Amends to Licenses DPR-58 & DPR-74,changing Tech Spec Sections 3/4.6.5.1 - 3/4.6.5.3 for Unit 1 & Section 3/4.6.5.1 for Unit 2,to Make Ice Condenser Tech Specs Identical

ML17334A851
Person / Time
Site:	Cook
Issue date:	12/28/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17334A853	List: ML17334A851 ML17334A855
References
AEP:NRC:0900, AEP:NRC:900, NUDOCS 8501020241
Download: ML17334A851 (9)

Text

REGULATOf INFORMATION DISTRIBUTION TEM (RIDS)

/'CCESSION NBR;8501020241 DOC ~ DATE: 84/12/28 NOTARIZED: NO. DOCKET ¹ FACIL:50-315 Donald C. Cook Nuclear Power Planti Unit 1< Indiana 8 05000315 50-316 Donald C ~ Cook Nuclear Power Plant~ Unit BYNAME 2~ Indiana R 05000316 AUTH AUTHOR AFFILIATION ALEXICH,M.P,- Indiana L Michigan Electric Co, RECIP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ RE Office of Nuclear Reactor Regulationr Director SUBJECT! Application for amends to Licenses DPR 58 8 DPR.74ichanging Tech Spec Sections 3/4.6,F 1 - 3/4.6 '.3 for Unit 1 Section 3/4,6,F 1 for Unit 2rto make ice condenser Tech Specs identical'ISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL "SIZE:

TITLE: OR Submittal: General Distribution NOTES; 05000315 OL: 10/25/74 05000316 OL; 12/23/72 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 01 7 7 INTERNAL; ACRS 09 6 ADM/LFMB ELD/HDS3 1 0 NRR/DE/MTEB NRR/DL DIR 1 1 NRR/DL/ORAB NRR/OSLO B 1 1 NRR/DSI/RAB FItX- 04 1 1 RGN3 EXTERNAL'PDR 03 2 2 NRC PDR 02 NSIC 05 1 1 NTIS TOTAL NUMBER Of COPIES REQUIRED: LTTR 27 ENCL 24

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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O, BOX 16631 COLUMBUS, OHIO 43216 December 28, 1984 AEP:NRC:0900 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR 74 ICE CONDENSER TECHNICAL SPECIFICATION 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/S) for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2. Specifically, we are proposing changes to T/S Section 3/4.6.5. 1 through 3/4.6.5.3 for Unit No. 1 and T/S Section 3/4.6.5. 1 for Unit No. 2.

These changes are intended to make the Unit Nos. 1 and 2 Ice Condenser T/S identical.

Attachment No. 1 to this letter contains the descriptions of the proposed ohanges and our analyses pursuant to 10 CFR 50.92 concerning significant hazards consideration. Attachment No. 2 to this letter contains the revised T/S pages.

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 effluents that may be released offsite, and (2) a significant increase in individual or cumulative occupational radiation exposure.

These proposed ohanges 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), a copy of this letter and its attachments have been transmitted to Mr. George Bruchmann of the Michigan Department of Public Health and Mr. R. C. Callen of the Michigan Public Service Commission.

Pursuant to 10 CFR 170. 12, we have enolosed a check in the amount of 4150.00 as payment for the application fee for the proposed T/S changes.

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Mi . Harold R. Denton AEP: NRC:0900 This document has been prepared following Corporate procedures which incorporate a reasonable set of contr ols to insure its acouracy and completeness prior to signature by the undersigned.

Very truly yours, M. P. exarch/)4 President 'ice th Attachmen t cc: John E. Dolan W. G. Smith, Jr. - Bridgman R. C. Callen G. Bruchmann G. Charnoff NRC Resident. Inspector - Bridgman .

ATTACHMENT NO. 1 TO AEP:NRC:0900 REASONS AND 10 CFR 50.92 ANALYSES FOR THE PROPOSED TECHNICAL SPECIFICATION CHANGES to AEP: NRC: 0900 Page 1 The first proposed change is to rewrite T/S 3.6.5.1.a for both Unit Nos. 1 and 2 to read as follows: ~The stored ice having a boron concentration of at least 1800 ppm (the boron being in the form of sodium tetraborate), and a pH of 9.0 to 9.5 at 25 C." Literal compliance with the current Technical Specification could result in an improper measurement of the boron concentration due to the ambiguity of the language used. This change removes this ambiguity by directly stating that it is the boron, not the sodium borate concentration that is to be measured . Xn addition, a temperatur e0 at which the pH of the boron solution is to be measured is specified to be 25 C. This change will not significantly affect either the boron concentration or the pH measurement. This specification will make reportig of pH values consistent with the industry practice of reporting values at 25 C. This change is primarily administrative in nature and thus, does not constitute a significant hazards consideration as defined by 10 CFR 50.92.

The second proposed change is to shorten the surveillance interval from 12 to 9 months in Unit No. 1 T/S 4.6.5. 1.b. This change makes the Unit 1 T/S identical to the respective Unit 2 T/S. This proposed change constitutes a more restrictive operating requirement, and ther efor e does not involve a significant hazards consideration as defined by 10 CFR 50.92.

The third proposed change is to rewrite T/S 4.6.5. 1.b. 1 for both Unit Nos.

1 and 2 to read as follows: "Chemical analyses which verify that at least 9 representative samples of stored ice have a boron concentration of at least 1800 ppm {the boron being in the form of sodium tetraborate), and a pH of 9.0 to 9.5 at 25 C." This proposed change is consistent with the first proposed change and is primarily administrative in nature. Therefore, this proposed change does not constitute a significant hazards consideration as defined by 10 CFR 50.92.

The fourth proposed change is to T/S 4.6.5. 1.b.2, for Unit 1 on page 3/4 6-27. Specifically, we are proposing that the ice condenser be subdivided into three groups of baskets as follows: "Group - bays 1 through 8, Group 2 >>

1 bays 9 through 16, and Group 3 - bays 17 through 24," instead of "Group 1-bays 1 through 7, Group 2 - bays 8 through 14, and Group 3 - bays 15 through 24." This change will make the Unit Nos. 1 and 2 T/S identical, and will make the T/S closer to the STS for Westinghouse Pressurized Water Reactors (NUREG-0452, Revision 4). The rationale for the initial groupings in Unit No.

1 T/S was closely tied to the initial ice weighings. The ice weighings which immediately followed the initial ice loadings indicated distinct differences in the ice weights as a function of the differ ent ice loading techniques.

Therefore, the 24 bays were originally divided into three groups on the basis of their original weights. There have since been several r eplenishments of ice in individual baskets. Subsequent reweighings have indicated that the initial distinct differences in the ice weights between groups such as those seen after the initial weighings have been eliminated. For these reasons, regrouping the baskets as proposed will not significantly affect public health and safety. We believe acceptable operation, in the proposed manner, has been demonstr ated by compliance with the identical and cur rently approved Unit 2 T/S. Therefore, this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.

to AEP:NRC:0900 Page 2 The fifth proposed change is to Unit No. 1 T/S 3.6.5.2, and is editorial in nature to make the two Units T/S read identically. Specifically, we are requesting that ACTION Statement a.3.(c) be changed to read "3 OPERABLE ref> igerant units" instead of ~3 OPERABLE 25 ton refrigeration chillers." This proposed change will also make the Unit NO. 1 T/S the same as the STS for Westinghouse Pressurized Water Reactors (NUREG-0452, Revision 4). This change is administrative in nature, and therefor e does not involve a significant hazards consideration as defined by 10 CFR 50.92.

The sixth proposed change is to the surveillance requirements for the ice condenser inlet doors, Unit No. 1 T/S 4.6.5.3.1. We propose that the operability of the doors be demonstrated at least once per 9 months by torque testing 50$ of the doors instead of at least once per 6 months with 25$ of the doors being torque tested. This change would allow us to demonstrate the operability of all doors in the shorter period of one refueling cycle (i.e.,

approximately 18 months). In addition, this change will make the interval for the torque testing of the doors consistent with the proposed ice basket weighing surveillance requirements (i.e., at least once per 9 months). We believe the proposed change is conservative since the total number of doors would be tested over a shorter time period. These changes would make the Unit No. 1 T/S identical to the respective Unit No. 2 T/S. Therefore this change does not involve a significant hazards consideration as defined by 10 CFR 50.92.

The seventh proposed change concerns editorial changes to the Unit 1 Technical Specifications pages 3/4 6-30 through 3/4 6-32. These changes would delete obsolete statements, clarify another statement, and make the Unit 1 T/S identical to the respective Unit 2 T/S. We propose that the following words be removed from T/S's 4.6.5.3. 1(b) and 4.6.5.3.2(b): "at least once per 3 months during the first year after the ice bed is fully loaded" and "thereafter." We propose T/S 4.6.5.3.2(a) be clarified to read "that opening of each door is not impaired by ice, frost or debr is" instead of "free of frost accumulation."

Finally, we propose that T/S 4.6.5.3.3 be revised to require the surveillance of the Top Deck Doors "once per 92 days" instead of "once per 3 months." These changes are administrative in nature, and therefore, do not involve a significant hazards consider ation as defined by 10 CFR 50.92.

The eighth proposed change is to rewrite the first sentence of Technical Specification 4.6.5.1.b.3 for both Units 1 and 2 to read as follows:

Verifying,, by a visual inspection of at least two flow passages per ice condenser bay, that the accumulation of frost or ice on flow passages between ice baskets, past lattice frames, through the intermediate and top deck floor grating, or past the lower inlet plenum support structures and turning vanes is restricted to a nominal thickness, of 3/8 inches. If one flow passage per bay is found to have an accumulation of frost or ice greater than this thickness, a representative sample of 20 additional flow passages from the same bay shall be visually inspected.

This change modifies the limiting ice thickness from 0.38 inches to a nominal 3/8 inches. This change is being done because the inherent nature of a visual inspection is not intended to provide accuracy to two decimal places as the current Technical Specification indicates. This change is considered primarily administrative in nature and thus, does not constitute a significant hazards consideration as defined by 10 CFR 50.92.

ATTACHMENT NO. 2 TO AEP:NRC:0900 PROPOSED TECHNICAL SPECIFICATION CHANGES