ML17325A639
| ML17325A639 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/29/1988 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17325A640 | List: |
| References | |
| NUDOCS 8803040361 | |
| Download: ML17325A639 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A, The application for amendment by Indiana Michigan Power Company (the licensee) dated January 11,
- 1988, 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; B.
The facility will operate in conformity with the application, 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 be conducted in compliance with the Commission's regulations; D.
The issuance of this 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.
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-74 is hereby amended to read as follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
99
, are hereby incorporated S8030403bi 850003kb 88022+:
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-2" 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 issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
February 29, 1988 Gary M. Holahan, Assistant Director for Regions III and V
Division of Reactor Projects - III, IV, V 5 Special Projects
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
99 FACILITY OPERATING LICENSE NO.
DPR-74 DOCKET NO. 50-316 Revise 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.
Corresponding overleaf pages are provided to maintain document conpleteness.
REMOVE
~s~ x-zz 3/4 5"5 3/4 5-8 3/4 7-21 INSERT
~ss x-n 3/4 5"5 3/4 5-8 3/4 7-21
REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS-OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 All shutdown and control rod position indicator channels and the demand position indication system shall be OPERABLE and capable of determining the control rod positions within + 12 steps.
APPLICABILITY:
NODES 1
and 2.
ACTION:
a
~
With a maximum of one rod position indicator channel per group inoperable either.
1.
Determine the position of the non-indicating rod(s) in<<
directly 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 iomediately after any motion of the non-i;ndicating rod which exceeds 24 steps in one direction since the last determination of the rod's position, or 2,'educe THERMAL POWER TO ~ S05 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 />, With a maxinum of'ne demand position indicator per bank i~operable either.
1,
'Verify that all.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 < 50K 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 />,
.SURVE ILLANCE REQUIREMENTS 4,1,3,2 Each rod position indicator channel shall be determined to be OPERABLE by verifying the demand position indication system and the rod position indicator channels 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 Noni'tor is inoperable, then compare the demand position indication system and the rod positi on i ndicator channels at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, D. C.
COOK - UNIT 2 3/4 1-21 Amendment No. 5h,.
99
REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS-SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 At least'ne rod position indicator channel (excluding demand position indication) shall be OPERABLE for each shutdown or control rod not fully inserted.
APPLICABILITY:
MODES 3c¹, 4x¹ and 5*
ACTION'ith less than the above required position indicator channel(s)
- OPERABLE, immediately open the reactor trip system breakers.
SURVEILLANCE RE UIREMENTS 4.1.3.3 Each of the above required rod position indicator channel(s) shall be determined to be OPERABLE by performance of a CHANNEL FUNCTIONAL TEST at least once per 18 months.+
- With the reactor trip system breakers in the closed position.
¹ See Special Test Exception 3.10.5.
+ The provisions of Specification 4.0.7 are applicable.
D.
C.
COOK - UNIT 2 3/4 1-22 Amendment No. Ni 99
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS Continued d.
At least once per 18 months by:
Verifying automat c isolation and interlock action of the RHR system from the Reactor Coolant System when the Reactor Coolant System pressure is above 600 psig.*
2.
A visual inspection of the containment sump and verifying that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks,
- screens, etc.)
show no evidence of structural distress or corrosion.
e.
At least once per 18 months, during shutdown, by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position qn a Safety Injection test signal.
2.
Verifying that each of the following pumps start automatically upon receipt of a safety injection test signal:
a)
Centrifugal charging pump b)
Safety injection pump c)
Residual heat removal pump f.
By verifying that each of the following pumps develops the indicated discharge pressure on recirculation flow when tested pursuant to Specification 4.0.5:
1.
Centrifugal charging pump
> 2405 psig 2.
Safety Injection pump
> 1445 psig 3.
Residual heat removal pump 195 psig g.
By verifying the correct position of each mechanical stop for the following Emergency Core Cooling System throttle valves:
1.
Vithin 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of each valve stroking operation or maintenance on the valve when the ECCS subsystems are required to be OPERABLE.
The provisions of Specification 4.0.7 are applicable.
D.
C.
COOK - UNIT 2 3/4 5-5 Amendment No. P7, 99
EHERGENCY. CORE COOLING SYSTEHS SURVEILLANCE RE UIREHENTS 4.5.3.1 The ECCS subsystem shall be demonstrated OPERABLE per the applicable Surveillance Requirements of 4.5.2.*~**-
- 4. 5.3.2 All charging pumps and safety injection pumps, except the above required OPERABLE charging pump, shall be demonstrated inoperable, by verifying that the motor circuit breakers have been removed from their electrical power supply circuits, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> wh'enever the tempe'rature of one or more of the RCS cold legs is less than or equal to 152~F as determined at least once per hour when any RCS cold leg temperature is between 152'F and 200'F.
- The provisions of Specification 4.0.6 are applicable.
- "'The nrovisions of Specification 4.0.7 are apnlicable.
D.
C.
COOK - UNIT 2 3/4 5-8 Amendment No. gP, 99
PLANT SYSTEHS SURVEILLANCE REOUIREHENTS Continued) b.
Visual Ins ection Acce tance Criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up.
Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and determined OPERABLE per Specification 4.7.7. l.d as applicable.
- However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERABLE via functional testing for the purpose of establishing the next visual inspection interval.
All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
c.
Functional Tests+
At least once per i8 months during shutdown, a representative sample (10~) of the total of each type of "nubber ir use in the plant shall be functionally tested either in place or in a bench test.
For each snubber that does not meet the functional :est acceptance criteria of Specification 4.7.7.1.d an additional 10>> of that type of snubber shall be functionally tested.
The representative sample selected for functional testing shall include the various configurations, operating environments and the range of size and capacity of snubbers.
At least 25" of the snubbers in the representative sample shall include snubbers from the following three categories:
1.
2.
3.
The first snubber away from each reactor vessel nozzle Snubbers within 5 feet of heavy equipment (valve,
- pump, turbine, motor, etc.)
Snubbers within 10 feet of the discharge from a safety relief valve Snubbers identified in Table 3.7-9 as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.>>
- Permanent or other exemptions rom functional testing for individual snubbers in these categories may be granted by the Commission only if a justifiable basis for exemption is presented and/or snubber life destructive testing was performed to qualify snubber operability for all design conditions at either the completion of their fabrication or at a subsequent date.
+ The provisions of Specification 4.0.7 are applicable.
D.
C.
COOK - UNIT 2 3/4 7-21 Amendment No.
99