ML20247L348

Application for Amend to License DPR-3,eliminating cycle-specific Operating Limits from Tech Specs & Including Operating Limits in Core Operating Limits Rept,Per Generic Ltr 88-16

ML20247L348
Person / Time
Site:	Yankee Rowe
Issue date:	09/14/1989
From:	Stephen Schultz YANKEE ATOMIC ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247L354	List: ML20247L348 ML20247L358
References
BYR-89-141, GL-88-16, NUDOCS 8909220188
Download: ML20247L348 (4)

Text

y, ; . ,

T IANKEYATOMICELECTRICCOMPANY 'Q"l$*g*gT;"i"l" 3

fjugm m.

580 Main Street, Bolton, Massachusetts 01740-1g98 September 14, 1989 PC 230 BYR 89-141 U *ted States Nuclear Regulatory Commission

. Document Control Desk Washington, DC 20555

References:

(a) License No. DpR-3 (Docket No. 50-29)

(b) Letter, USNRC to YAEC, Generic Letter 88-16

Subject:

proposed Change to Eliminate the Cycle-Specific parameter Limits from the Yankee Technical Specifications

Dear Sir:

Pursuant-to Section 50.59 of the Commission's Rules and Regulations, Yan'kee Atomic Electric Company (Yankee) hereby proposes the following change to Appendix A of the Operating License (Reference (a)).

Proposed Change Yankee proposes to change its Technical Specifications by eliminating the cycle-specific operating limits from various sections of the Yankee Technical Specifications; listing the approved methods; and describing the Core Operating Limits Report (COLR), Which will contain the cycle-specific limits.

The changes were in response to the NRC generic letter (Reference (b)), which encouraged all licensees and applicants to eliminate the cycle-cpecific limits from the Technical Specifications. The wording in the changes was also obtained from Reference (b). The proposed changes and revised pages are listed in Table 1. Attachment 1 contains the revised pages.

Reason for Change Yankee presently generates the cycle-specific limits for each cycle using NRC-approved methods. For each cycle, Yankee gen 6 rates and the NRC reviews a proposed Technical Specification change to the cycle-specific limits. This is an administrative burden on the NRC staff and Tankee because the limits are

. similar and the methods are the same for each cycle. The NRC recognizes this burden and has recommended that all licent,ees climinate the cycle-specific limits from their Technical Specifications (Reference (b)). Therefore, Yankee proposes these changes following the recommendations in Reference (b).

fY t 4

\

&?O9220188 890914 PDR P ADOCK 05000029 FDC e--:--._----

/ cL t  : *E

- R *.

( *

. United States Nuclear Regulatory Commission ' September 14, 1989 Document Control Desk page 2 BYR 89-141 Bases for Channes The cycle-specific limits will still be calculated for each cycle using NRC-approved. methods. The cycle-specific limits will be documented and provided to the NRC in the COLR. Attachment 2 provides a sample format for this report. The Technical Specifications will still require the plant to  ;

operate within these limits and to take the appropriate action should the i

limits be exceeded.

'These changes conform to the guidelines provided in ERC Generic

. Letter 88-16 (Reference (b)). ,

)

l

' Safety Considerations These proposed changes do not present any unreviewed safety questions as defined in 10CFR50.59(a)(2). The cycle-specific operating limits will be defined using approved methods Which will be listed in Section 6.9.4 of the Technical Specifications. The Technical Specifications will continue to ,

require operation within the cycle-specific limits for each cycle. The limits will be listed in' the COLR for each cycle and be sent to the NRC for I information. These changes have been reviewed by the Plant Operations Review Committee (PORC) and the Nuclear Safety Audit and Review Committee (NSARC).

Significant Hazards Consideration 10CFR50.92 states that a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not:

(i) involve a significant increase in the probability or consequences of an ,

1 accident previously evaluated; or (ii) create the possibility of a new or different kind of accident from any accident previously evaluated; or (iii) involve a significant reduction in a margin of safety. The discussion below  ;

addresses these standards, and demonstrates that operating the facility with I these proposed changes involves no significant hazards considerations:

1. The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated because the cycle-specific limits will still be determined by i analyzing the same postulated events previously analyzed. The plant  !

will continue to operate within the limits specified in the COLR and to take the same actions when or if the limits are exceeded as required by current Technical Specifications.

2. The proposed changes do not create the possibility of a new or different kind of accident previously evaluated because no physical alterations of plant configuration, changes to setpoint, or safety limits are proposed.

3. The proposed changes do not involve a significant reduction in a safety margin because they do not affect any operating practices, limits, or safety-related equipment. The cycle-specific limits, specified in the COLR, will continue to be defined using approved methods which will be defined in the Technical Specifications. Each

i, ,: *

.l C.

e 1

United States Nuclear Regulatory Commission September 14, 1989 L

Document Control Desk Page 3 BYR 89-141 future reload will be reviewed to ensure that operation within the cycle-specific limits will not involve a significant reduction in a margin of safety.

Schedule for Changes These changes will be incorporated into the Yankee Technical Specifications 1.4 soon as practicable following receipt of your approval.

We trust that the information above edequately supports our request; however, should you have any questions in this matter, please contact us.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY 5

S. P. Schultz Vice President BLD/mma/0428u Attachments COMMONWEALTH OF MASSACHUSETTS) '

)ss MIDDLESEX COUNTY )

Then personally appeared before me, S. P. Schultz, who, being duly sworn, did state that he is Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing document in the name and on the behalf of Yankee Atomic Electric Company and that the statements therein are true to the best of his knowledge and belief.

v< & h Robert H. Groce Notary Public My Commission Expires August 29, 1991

• i

. . j c . .  ?

l 9

TABLE 1 l Proposed Technical Specification Changes Change Page

1.0 DEFINITIONS

Add 1.36 Core Operating Limits Report 1-6 3/4.1 REACTIVITY CONTROL SYSTEMS:

LCO 3.1.3.1 Replace Reference to Figure 3.1-2 with Reference to COLR 3/4 1-24 LCO 3.1.3.5 Replace Reference to Figure 3.1-2 with Reference to COLR 3/4 1-28 LCO 3.1.3.5 Delete Figure 3.1-2 3/4 1-29 1

Bases 3.4.1.1 Replace Reference to Figure 3.1-2 with Reference to COLR B3/4 1-1 3/4.2 POWER DISTRIBUTION LIMITS: j LCO 3.2.1 Replace References to Figure 3.2-1 with Reference to COLR 3/4 2-1  !

SR 4.2.1.1 Replace Reference to Figure 3.2-1 with Reference to COLR 3/4 2-1 SR 4.2.1.2 Replace References to Figures 3.2-3 and 3.2-4 with References to COLR; remove specific values for rod insertion limits from " Exceptions". These values were provided in Figure 3.2-1 and will now be provided in the COLR 3/4 2-2 LCO 3.2.1 Delete Figure 3.1-1 3/4 2-4 SR 4.2.1.2 Delete Figure 3.2-3 3/4 2-0 SR 4.2.1.2 Delete Figure 3.2-4 3/4 2-7 Bases 3/4.2.1 Replace Reference to Figure 3.2-3 with Reference to COLR B3/4 2-1 Replace Reference to Figure 3.2-1 with Reference to COLR B3/4 2-2 6-9 REPORTINC REQUIREMENTS: Add 6.9.4 Core Operating Limits Report 6-16 l

l l

0428u l' - - - - _ _ - - - - - _ - _ _ - - - -