ML20079D648
| ML20079D648 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 07/12/1991 |
| From: | Shiraki C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079D649 | List: |
| References | |
| NUDOCS 9107230329 | |
| Download: ML20079D648 (6) | |
Text
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UNITED STA1Es g
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10WA ELECTRIC LIGHT AND POWER COMPANY CtNTRAL IDWA POWER COOPERATIVE CORN BELT POWER COOPERATl W DOCKET NO. 50-331 j
DUANE ARNOLD ENERGY CENTER
- AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 171 License No. DPR-49 i
.1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
Th'e application for amendment by Iowa-Electric Light and Power Company. et al., dated-December 14, 1990 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.
.Thereisreasonableassurance-(i)thattheactivitiesauthorized 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 i
defense and security or to the health and safety of the public; and E.
The 1ssuance 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 Specifi-
' cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
t
'9107230329 910712 ADOCK 05 ] l1 PDR-
. i (2) lechnicalSpecifications f
The Technical Specifications contained in Appendix A, as revised through Amendment No.171, are hereby incorporated in the license. The licensee shall operate the facility in accordance w!'h the Technical Specifications.
The license amendment is effective as of the date of issuance and 3.
shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION y
Clyde Y. Shiraki, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
July 12, 1991
ATTACHMENT TO LICENSE AMENDMENT NO.171 FACILITY OPERATING LICENSE NO. OPR-49 i
DOCKET NO. 50-331 Replace the following pages of the Appendix A Technical Specifications with 1
the enclosed pages. The revised areas are indicated by marginal lines.
t Pages MB 3.7-13 i
3.7-26
DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT maintain the remainder of the secondary containment at 1/4 inch of water negative pressure under calm wind conditions.
l 2.
If Specification 3.7.C.1 cannot be met:
a.
Suspend reactor building fuel cask and irradiated fuel movement, and b.
Restore secondary containment integrity within one hour; or, c.
Be in COLD SHUT 00VN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D.
Primary Containment Power Ooerated D.
Primary Conta inment Power Operated Isolation Valves Isolation Va' ves 1.
The primary containment isolation 1.
During reactor power operatin9 w ives surveillance shall be conditions, all isolation valves performed as follows:
listed in Table 3.7-3 and all instrument line flow check valves a.
At least once per erating cycle the OFERABLE isolat on valves that shall be OPERABLE except as are power operated and specified in 3.7.0.2.
automatically initiated shall be tested for simulated automatic initiation and closure times.
b.
At least once per quarter:
1)
All normally open power operated isolation valves (except for those exempted as noted in Table 3.7-3) shall be fully closed and reopened.
2)
With the reactor power less than 75%, trip main steam isolation valves individually and verify closure time, c.
At least once per operating cycle the operability of the reactor coolant system instrument line flow check valves shall be verified.
- Intent Change Only (definition of operating cycle).
~
Amendment No. 729,J A3,171
i DAEC-1 LIMITING CONDITION FOR OP: RATION SURVEILLANCE REQUIREMENT l
2;
'w'ith one or more of the primary I
j containment isolation ' valves shown j
in Table 3.7-3 inoperable (except i
for those exempted as noted in Table 3.7-3), maintain at 1 erst i
i
-l one isolation valve OPERABLE
- or I
ISOLATED" and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> j
either:
i a.
Restore the inoperable valve (s) to. OPERABLE status,-
or b.
Isolate each affected penetration by use of at least
-one automatic valve __ locked or electrically deactivated in the isolated position," or
~
c.
Isolate each ffected penetration by use of at least one manual valve locked in the isolated position or blind flange."
3.
If Specification 3.7.D.1, and 3.7.0.2 cannot be met, an orderly shutdown shall.be initiated and.
the reactor.shall be in the Cold.
. Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- This valve may be locked or -
electrically deactivated as noted in
' Subsection 3.7.D.2.b.
" Isolation valves. closed to satisfy these-requirements may be reopened on an intermittent basis under administrative control.
o:
l I
Amendment _No. 78,JA3,J/6, 171 3.7-19
n DAEC - 1 TABLE 3.7-3 (Continued)
PRIMARY CONTAINMENT POWER OPERATED ISOLATION VALVES Number of Maximum Isolation Power Operating Action on Group Operated Time Normal Initiating (Note 1)
Valve Identification Valves (Seconds)
Position Signal 5
RWCU Supply 2
20 0
GC 5
RWCU Return 1
10 0
GC 6
Steam to HPCI Turbine 2
13 0
GC 6"**
HPCT Discharge to 1
20 C
GC Feedwater 6
Steam to RCIC Turbine 2
20 0
GC 6***
RCIC Discharge to 1
15 C
GC Feedwater 8
Condensate from HPCI 2
NA 0
GC 8**
Condensate from RCIC 2
NA 0
GC 3
- Containment Compressor 3
NA 0
GC Discharge 7
- Reactor Building 2
20 0
GC Closed Cocling Water Supply / Return 7
- Well Cooling Water 4
NA 0
GC Supply / Return 9
HPC1/RCIC Exhaust 2
10 0
GC Vacuum Breaker 3
Post-Accident Sampling 2
NA C
SC Liquid Sample Return 3
Post-Accident Sampling 4
NA C
SC Jet Pump Sample
- Due to plant operational limitations, these valves will be subject to the I requirements of 4.7.0.1.a except for the MSIVs which will be subject to the I requirements of 4.7.0.1.b.
- Low-Low Water Level Only
- These valves close only upon sensing closure of their respective turbine steem supply or turbine stop valve closure.
l l
Amendment No. J23,73E,171 3.7-26
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