ML20213F481

Proposed Tech Spec 3.1.3.1,allowing Continued Operation for 72h W/One or More Rod Assemblies Inoperable Due to Electrical Problems in Rod Control Sys.Fee Paid

ML20213F481
Person / Time
Site:	Wolf Creek
Issue date:	05/07/1987
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20213F462	List: ML20213F460 ML20213F481
References
NUDOCS 8705150341
Download: ML20213F481 (6)

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ATTACHMENT III PROPOSED TECHNICAL SPECIFICATION CHANGES 0705150341 670507 PDR ADOCK 00000482 p PDR I

. Attachment III to ET 87-0178 Page 1 of 5 Mby 7, 1987 REACTIVITY CONTROL SYSTEMS ,.

4/4.1.3 MOVABLE CONTROL ASSEMBLIES q [

j GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within i 12 steps (indicated position) of their group step counter demand position.

APPLICABILITY: MODES 1* and 2*.

ACTION: INSERT A

"__ith :n:_,er____,,:~_

_ __...i. ;re full-length

,_ ,.:__ __ red; insperable

__,u _:,,, due te being

<_.__,______ __ in:: :b!:

ACTION 1 - 5 :Ur't$"$$ Ukt ihh$5iE, k erminel. hat be ShbTD05h'M RG b require-ment of Specification 3.1.1.1 is satisfied within I hour and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. "ith ::re ther ca full-length red in;perable er ri; ligned fr;; the i;rcup step counter de nd p::ition by cre than 212 :tep: (indicated ACTION 2 - p;;ition),feinHOTSTANDBYwithin6 hours.

c. uit3 ene fg7i_7g ts. g cd tripp-b': but incpe ab!: due t: ::ucc:

ether th r addre;;cd by ^CTIC" . ab:ve, or -i:21igned 'rcr its gr;up :t p : unter d: end height by cre than i 12 step: (indicated ACTION 3 - pccitien), POWER OPERATION may continue provided that within 1 hour: 4

1. The rod is restored to OPERABLE status within the above alignment requirements, or

2. The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figures 3.1-1 and 3.1-2. The THERMAL POWER level shall be restricted pursuant to Specifica-tion 3.1.3.6 during subsequent operation, or

3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. POWER OPERATION may then continue provided that; a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

• See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

WOLF CREEK - UNIT 1 3/4 1-14 L

. Attachment III to ET 87-0178 Page 2 of 5

, - May 7,1987

' REACTIVITY CONTROL SYSTEMS

('

LIMITING CONDITION FOR OPERATION ACTION (Continued) c) A power distribution map is obtained from the movable incore detectors and F9(Z) and F g are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; and d) The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED

, THERMAL POWER.

ACTION 4 - Restore the inoperable rods to OPERABLE status wit in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full-length rod shall be determined to be within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the rod position deviation monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

WOLF CREEK - UNIT I 3/4 1-15..

. Attachment III to ET 87-0178 Page 3 of 5 May 7, 1987 REACTIVITY CONTROL SYSTEMS

( ,

6 BASES 80 RATION SYSTEMS (Continued) ,

With the RCS temperature below 200*F, one Boration System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection System becomes inoperable.

The limitation for a maximum of one centrifugal charging pump to be '

OPERABLE and the Surveillance Requirement to verify all charging pumps except a the required OPERA 8LE pump to be inoperable in MODES 4, 5, and 6 provides assurance that a mass addition pressure transient can be relieved by the opera-tion of a single PORV or an RHR suction relief valve.

The boron capability required below 200 F is sufficient to provide a SHUT 00WN MARGIN of 1% Ak/k after xenon decay and cooldown from 200 F to 140 F. This condition requires either 2968 gallons of 7000 ppm borated water from the boric acid storage tanks or 14,076 gallons of 2000 ppm borated water from the RWST.

i The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The OPERABILITY of one Boration System during REFUELING ensures that this system is available for reactivity control while in MODE 6.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that: (1) acceptable power

-distribution limits are naintained, (2) the minimum SHUTOOWN MARGIN is main-tained, and (3) the potem ial effects of rod misalignment on associated acci-dent analyses are limited. OPERABILITY of the control rod position indicators is required to determine ccitrol rod positions and thereby ensure compliance with the control rod alignmiit and insertion limits. Verification that the Digital Rod Position Indicatc' agrees with the demanded position within 12 steps at 24, 48, 120, and 228 .teps withdrawn for the Control Banks and 18, 210 and 228 steps withdrawn for the Shutdown Banks provides assurances that the Digital Rod Position Indicator is operating correctly over the full range of 1 indication. Since the Digital Rod Position System does not indicate the actual shutdown rod position between 18 steps and 210 steps, only points in the indicated ranges are picked for verification of agreement with demanded position.

WOLF CREEK - UNIT 1 B 3/4 1-3

. Attachment III to ET 87-0178 Page 4 of 5 Nay 7, 1987 REACTIVITY CONTROL SYSTEMS k

BASES MOVABLE CONTROL ASSEMBLIES (Continued)

ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement of peaking factors and a restriction in THERMAL POWER. These restrictions provide assurance of fuel rod integrity during continued operation. In addition, those safety analyses affected by a misaligned rod are reevaluated to confirm that the results remain valid during future operation.

, The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with T,yg greater than or equal to 551*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a Reactor trip at operating conditions.

Control rod positions and'0PERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable. f These verification frequencies are adequate for assuring that the applicable LCOs are satisfied. (

WOLF CREEK - UNIT 1 8 3/4 1-4 4 _ _ - ,

~a Attrohment III to ET 87-0178 Page 5 of 5 May 7,1987 Technical Specification Inserts Insert A The ACTION to be taken is based on the cause of inoperability of control rods as follows:

ACTION More Than CAUSE OF INOPERABILITY One Rod One Rod a) Immovable as a result of excessive (1) (1) friction or mechanical interference or known to be untrippable.

b) Misaligned from its group step (3) (2) counter demand height or from any other rod in its group by more than

+ 12 steps (indicated position).

c) Inoperable due to a rod control urgent (4) (4) failure alarm or other electrical problem in the rod control system, but trippabl?.

Insert B For purposes of determining compliance with Specification 3.1.3.1, any immovability of a control rod invokes ACTION Statement 3.1.3.1.a Before utilizing ACTION Statement 3.1.3.1.c, the rod control urgent failure alarm must be illuminated or an electrical problem must be detected in the rod control system. The rod is considered trippable if the rod was demonstrated OPERABLE during the lest performance of Surveillance Requirement 4.1.3.1.2 and met the rod drop time criteria of Specification 3.1.3.4 during the last performance of Surveillance Requirement 4.1.3.4.

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