ML17319B425
| ML17319B425 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/28/1982 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17319B426 | List: |
| References | |
| NUDOCS 8207150616 | |
| Download: ML17319B425 (5) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 8207i506ih 820628 PDR
- DOCK 050003i5 P
PDR INDI'ANA.AND MI'CHIGAN ELECTRIC COMPANY DOCKET NO. 50-315 DONALD C.
COOK NUCLEAR PLANT, UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The request for amendment by I'ndiana and Michigan Electric Company (the licensee) dated June 7, 1982, 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 tn 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 COIImIission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the hea'Ith 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 5'I of the Commission's regulations and all applicable requirements have been satisfied.
2 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(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 55
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment was effective June 7, 1982.
'THE NUC
'EGULATORY COMMISSION n
aV a
Attachment:
Changes to the Technical Specifications Operating Reactors Division of Licen i ranch
¹1 g
Date of Issuance:
June 28, 1982
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
55 TO FACILITY OPERATING LI:CENSE NO.
DPR-58 DOCKET NO. 50-315 Revise Appendix A as fo11ows:
Remove Pa es 3/4 5-3 3/4 5-4*
Insert Pa es 3/4 5-3 3/4 5-4*
- Inc1uded for convenience
EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T
> 350'F LIMITING CONDITION fOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:
a.
One OPERABLE centrifugal charging
- pump, b.
One OPERABLE safety injection pump, c.
One OPERABLE residual heat removal heat exchanger, d.
One OPERABLE residual heat removal
- pump, and e.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recir-culation phase of operation.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
a.
b.
With one ECCS subsystem inoperable, restore the inoperable sub-system to OPERABLE status within 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
In the event the ECCS is actuated and injects water into the Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
+After June 10, 1982, the Action shall be
- a. with one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN.within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D.C.COOK-UNIT 1
3/4 5-3 Amendment No.
55
EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE RE UIREMENTS 4.5.:2 Each ECCS subsystem shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED, TEST BASIS by:
1.
Verifying that each centrifugal charging pump:
a)
Starts (unless already operating) from the control room.,
b)
Develops a discharge pressure of > 2405 psig on recirculation flow.
c)
Operates for at least 15 minutes.
2.
Verifying that each safety injection pump:
a)
Starts (unless already operating) from the control room.
b)
Develops a discharge pressure of ~ 1445 psig on recirculation flow.
c)
Operates for at least 15 minutes.
3.
Verifying that each residual heat removal pump:
a)
Starts (unless already operating) from the control room.
b)
Develops a discharge pressure
~ 195 psig on recirculation flow.
c)
Operates for at least 15 minutes.
4.
Verifying that the following valves are in the specified positions with control power locked-out:
Valve Number a.
IMO-390 b.
IMO-315 c.
IMO-325 Valve Function a.
RMST to RHR b.
Low head SI to Hot Leg c.
Low head SI to Hot Leg Valve Position a.
Open b.
Closed c.
Closed D. C.
COOK-UNIT 1 3/4 5-4 Amendment No.