ML20195K140

Amend 110 to License DPR-3,revising Tech Specs Re Control Rod Position Indication & Correcting Minor Error in Tech Specs

ML20195K140
Person / Time
Site:	Yankee Rowe
Issue date:	06/17/1988
From:	Wessman R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195K130	List: ML20195K124 ML20195K140 ML20195K150
References
NUDOCS 8806290354
Download: ML20195K140 (6)

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1. h L'NITED STATES l

[ ] ; e, h NUCLEAR REGULA(ORY COMMISSION g- .; WASHING TON, D. C. 20555 l i

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i YANKEEATOMICELECTRICCOMPAR YANKEE NUCLEAR POWER STATION DOCKET N0.50-029 AMENDMFNT TO FACILITY OPERATING LICENSE Amendment No. 110 License No. DPR-3

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment by Yankee Atomic Electric Company (thelicensee)datedDecember 23, 1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as cmended (tha Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I;

8. The facility will operate in conformity with the application, the provisions of the Ac.t. and the rules and regulations of the Comission; C. Thare is reasonab7.e assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have i been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-3 is hereby amended to read as follows:

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2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 110 , are nereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY C0FNISSION Nt h Richard H. Wessman, Director Project Directorate 1-3 Division of Reacto- Projects I/II

Attachment:

Changes to the Technical Spacifications Cete of Issuance: June 17, 1988 1

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6 ATTACHMENT TO LICENSE AMENDMENT-Nr .110 FACILITY OPERATING LICENSE NO. DPR-3 DOCKET-NO.50-029 Revise Appendix A Technical Specifications by renoving_the'page identifiad below and inserting the enclosed paqe. The revised page is identified by the.

captioned amendment number and contains marginal . lines indicating the area of change.

REMOVE INSERT 3/4 1-75 3/4 1-25 ~!

R 3/4 1-3 B 3/4 1-3* '

B 3/4 1-4 8 3/4 1-4  ;

• Unchanged, overleaf page . .

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. REACTIVITY CONTROL SYSTEMS -

POSITION INDICATOR CHANNE M LIMITING CON 1;ITION FOR OPERATION 3.1.3.2 All control rod primary and secondary position indicator channels shall be OPERABLE and capable of determining the control rod positions within 18 inches. l APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one primary rod position indicator channel per group inoperable either:

1. Determine the position of the non-indicating rod (s) indirectly by the incore detectors at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and immediately l af ter any motion of the non-indicating rod which exceeds 8 inches in one direction since the last determination of the rod's position, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. With a maximum of one secondary position indicator per group inoperable, either:

1. Verify that all primary rod position indicators for the affected group are OPERABLE, or l

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within  !

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

SURVEILI.ANCE REQUIREMENTS l

4.1.3.2 Each rod position indicator channel shall be determined to be l OPERABLE by verifying the primary position indication system and the secondary position indicator channels agree within 8 inches at leat t once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. l 1

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YANKEE R0WE 3/4 1-25 Amendment No. 110 i

3/4.1 R_ ACTIVITY :0NTROL SYSTEMS BASES 4

3/4.1.2 80 RATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include 1 borated water sources, 2) charging pumps, 3) separate flow paths fru the borated water sources to the charging pumps, 4) boric acid gravity flow connection, 5) associated heat tracing systems, and 6) power supply from OPERABLE 480 volt busses.

flow paths.

Allowable out-of-service periods ensure that minor component repair or corrective action may be completed without undue risk to overall facilicy safety from injection system failures de"ing the repair period.

The boration capability is sufficient to provide a SHUTDOWN MARGIN from all operating conditions of 5.0% ak/k after xenon decay and cooldown to 200*F. The maximum boration capability requirement occurs at EOL from full power equilibrium xennr. conoitions and requires 776 gallons of 22,000 ppm borated water from the boric acid mix tank or 9192 gallons of 2200 ppn; borated water from the safety injection tank.

With the Main Coolant System temperature below 200*F, except during refueling, one charging pump is acceptable without single failure con-sideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting positive reactivity change in the event the single charging pump becomes inoperable.

The beron capability required below 200*F is sufficient to provide a SHUTDOWN MARGIN of 7% ak/k af ter xenon decay and cooldown from 200*F to 140*F. This condition requires either 1059 gallons of 22,000 ppm l barated water from the boric acid mix tank or 13,218 gallons of 2200 ppm borated water from the safety injection tank.

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YANKEE-ROWE B 3/41-3 Mendment No. 110

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3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.3 MOVABLE CONTROL RODS The specifications of this ection ensure that (*.) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, (3) the individual control rod worth and hot channel factors used for the accident analyses are not exceeded, and (4) limit the potential effects of a rod ejection accident. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

For control rod misalignment up to 8 inches from every other control rod in its group and for all control rod groups within their insertion limite, the hot channel factors will be well within the design limits of:

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H If a control rod is misaligned the hot channel factors, potential ejected rod worth, and SHUTDOWN MARGIN will be shown to be within design limits and reactor power will be reduced. The requiremer' ' hat no more than one inoperable control rod is allowed and that the sht. margin is maintained ensures that the reactor can be brought to c afe shutdown condition at any time.

The ACTION statemerts which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met. Misalignment of a rod requires ejected rod worth and SHUTDOWN MARGIN to be within limits and a restriction in THERMAL POWER; either of these restrictions provide YANKEE-ROWE B 3/4 1-4 Amendment No. y),110

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