ML20076B424
| ML20076B424 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/27/1991 |
| From: | Dick G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076B428 | List: |
| References | |
| NUDOCS 9107110231 | |
| Download: ML20076B424 (10) | |
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UNITED STATES-3 ' 9 [i -
NUCLEAR REGULATORY COMMISSION
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WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-42 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation),
dated March 20, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; 4
B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable 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 De conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
9107110231 910627 PDR ADOCK 05000482 P
s,
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment.and Paragraph 2.C.(2) of Facility Opervting License No.-NPF-42 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 46, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license.
The Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
q wyc Georde F. Dick, J r., Acting Director Project Directorate IV-2 Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Reguistion
Attachment:
Changes to the Technical Specifications Date of Issuance: June 27, 1991 4
L
4 ATTACHMENT TO LICENSE AMENDMENT NO. 46 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET NO. 50-482 Revice Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by amendment number and contain marginal lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT 3/4 1-14 3/4 1-14 3/4 1-17 3/4 1-17 3/4 1-17a B 3/4 1-4 8 3/4 1-4 l
l
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i 1
ImL REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.2.6 Each required borated water source shall be demonstrated OPERABLE:
j a.
At least once per 7 days by:
1)
Verifying the boron concentration in the water, 2)
Verifying the contained borated water volume of the water source, and 3)
Verifying the Boric Acid Storage System solution temperature when it is the source of borated water.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is either less than 37'F or greater than 100*F.
t WOLF CREEK - UNIT 1 3/4 1-13
REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES 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:
The ACTION to be taken is based on the cause of inoperability of control rods as follows:
ACTION More Than CAUSE OF INOPERABILITY 3ne 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 cthe,' electrical problem in the rod control system, but trippable.
ACTION 1 - Determine that the SHUTDOWN MARGIN requirement 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 />.
ACTION 2 - 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 />.
ACTION 3 - P0 DER OPERATION may continue provided that within 1 hour:
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 Figure 3.1-1.
The THERMAL POWER level shall be restricted pursuant to Specifica-tion 3.1.3.6 during subsequent operation, or rsee Special Test Exceptions Specifications 3.10.2 and 3.10.3.
WOLF CREEK - UNIT 1 3/4 1-14 Amendment No. 27, 46
REACTIVZTY CONTROL SYSTEMS POSITION INDICATION SYSTEMS-OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod Position Indication System and the Demand Position 4
I Indication System shall be OPERABLE and capable of determining the control rod positions within i 12 steps.
APPLICABILITY:
MODES 1 and 2.
ACTION:
a.
With a maximum of one digital rod position indicator per bank inoper-able either:
1.
Determine the position of the nonindicating rod (s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the nonindicating rod which exceeds 24 steps in one direction since the last determination i
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 more than one digital rod position indicator per bank inoperable either:
1.a) Determine the position of the nonindicating rods indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the lionindicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, and b) Place the control rods under manual control, and c) Monitor and record Reactor Coolant System average temperature (T, g) at least once per hour, and d) Restore the digital rod position indicators to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> such that a maximum of one digital rod position indicator per bank is inoperable, or 2.
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 />.
WOLF CREEK - UNIT 1 3/4 1-17 Amendment No. 4f
REACT 1VITY CONTROL SYSTEMS POSITION INDICATION SYSTEMS-OPERATING LIMITING CONDITION FOR OPERATION (continued) c.
With a maximum of one demand position indicatot per bank inoperable either:
1.
Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of each other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, 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 />.
SURVEILLANCE REQUIREMENTS 4.1.3.2 Each digital rod position indicator shall be determined to be OPERABLE by verifying that the Demand Position Indi:ation System and the Digital Rod Position Indication System agree within 12 steps 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 inoper-able, then compare the Demand Position InJ: cation System and the Digital Rod Position Indication System at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
WOLF CREEK - UNIT 1 3/4 1-17a Amendment No. 46
m REACTIVITY CONTROL SYSTEMS POSITION INDICATION SYSTEM-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 One digital rod position indicator (excluding demand position indica-tion) shall be OPERABLE and capable of determining the control rod position within i 12 steps for each shutdown or control rod not fully inserted.
APPLICABILITY: HODES 3*#, 4*#, and S*#.
ACTION:
With less than the above required position indicator (s) OPERABLE, immediately open the Reactor Trip System breakers.
I SURVEILLANCE REQUIREMENTS 4.1.3.3 Each of the above required digital rod position indicator (s) shall be determined to be OPERABLE by verifying that the digital rod position indicator agrees with the demand position indicator within 12 steps when exercised over the full range of rod travel at least once per 18 months.
- With the Reactor Trip System breakers in the closed position.
- See Special-Test Exception Specification 3.10.3.
i WOLF CREEK - UNIT 1 3/4 1-18
~.. _.
REACTIVITY CONTROL SYSTEMS BASES BORATION 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 the required OPERABLE 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 2c0 F is sufficient to provide a SHUTOOWN MARGIN of 1% ak/k af ter xenon decay and cooldown from 200 F to 140*F.
This condition requires either 2968 gallons of 7000 ppm borated i
water from the boric acid storage tanks or 14,071 gallons of 2400 ppm borated I
water from the RWST.
The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.
In the case of the boric acid tanks, all of the contained volume is considered usuable.
The required usable volume may be contained in either or both of the boric acid tanks.
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 iodiae 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 maintained, (2) the minimum SHUTOOWN MARGIN is main-tained, and (3) the potential effects of rod misalignment on associated acci-dent analyses are limited.
OPEPABILITY 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.
Verification that the Digital Rod Position Indicator agrees with the demanded position within 12 steps at 24, 48,120, and 228 steps 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 indication.
Since the Digital Rod Position System does not indicate the actual l
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 Amendment No. 23
REACTIVITY CONTROL SYSTEMS i
BASES MOVABLE CONTROL ASSEMBLIES (Continued)
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 cont.ol 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 last 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.
The 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 f actors 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 power reduction and shutdown time limits given in ACTION statements 3.1.3.2.a.2, 3.1.3.2.b.2, and 3.1.3.2.c.2, respectively, are initiated at the time of discovery that the compensatory actions required for POWER OPERATION can no longer be met.
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 representati"a of insertion times experienced during a Reactor trip at operating conditions.
Control rod positions and OPERABILITY 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.
These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.
WOLF CREEK - UNIT 1 B 3/4 1-4 Amendment No. 27, 4
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