ML20155D262
| ML20155D262 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 09/30/1988 |
| From: | Hannon J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20155D266 | List: |
| References | |
| NUDOCS 8810110193 | |
| Download: ML20155D262 (13) | |
Text
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
3 WASHING TON, D. C. 20H6
%...+)
IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIkT.
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DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER i
AhENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al., dated August 31, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisiens of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment con be conducted without endangering the health and safety of the public, and (11) that such activities will be j
conducted in compliance with the Comission's regulations; i
D.
The issuance of this arrendrrent 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 i
fl of the Comission's regulations and a51 applicable requirerrents have been satisfied.
i 2
Accordingly, the license is amended by changes to the Technical Specif1-cations as indicated in the attachment to this license amendment and i
paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby j
amended to read as follows:
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FN.o2gGCK0500o333 in esoo2o i
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(2) Technical Specifications The Technical Specifications contained in Appendix A, i
^<5 revised through Amendment Fo.153, are hereby incorporated in the licente. The licensee shall operate the facility in l
accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
g
/ John N. Hannon. Directer Project Directorate !!!-3 Division of Reactor Projects - !!!,
IV, Y and Special Projects
Attachment:
Changes to tha Technical
$ptcifications Date of Issuance:
September 30, 1988 I
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j ATTACHMENT TO LICENSE AMENOMENT NO. 153
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FACILITY OPERATING LICENSE NO. OPR-49 DOCKET NO 50-331 j
Replace the following pages of the Appendix A Technical Specificatitri with i
q the enclosed pages.
The revised areas are indicated by marginal lines.
j REMOVE INSERT i
3.7-15 3.7-15 4
3.7-16 3.7-16 3.7-43 J.7-43 l
3.7-45a i
3.7-46 3.7-46
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3.7-47 3.7-47 i
3.8-4 3.8-4 l
3.9 4a 3.10-1 3.10-1 l
I 3.10-2 3.10-2 j
3.10-4 3.10 4 l
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l DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT (3.7)
(4.7) l B.
Standby Gas Treatment System B.
Standby Gas Treatment System 1.
Except as specified in 1.a. Annually it shall be demonstrated Specifications 3.7.B.3 and that pressure drop across the 3.9.D. both trains of the combined high efficiency and standby gas treatment system charcoal filters 15 less than shall be OPERABLE at all times 11 inches of water in the flow when SECONDARY CONTAIN'4ENT range of 3600 to 4000 cfm.
I INTEGRITY is required.
- b. Annually demonstrate that the inlet heaters on each train are l
capable of an output of at least 11 Kw.
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- c. Annually demonstrate that air distribution is unifonn within 20% of averaged flow per unit across HEPA filters.
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- d. Once per operating cycle automati.
initiation of each branch of the standby gas treatment system shall bt demonstrated, j
- e. Manual operability of the bypass system for filter cooling shall be demonstrated annually.
- f. System drains shall be inspected quarterly for adequate water level in loop seals,
- 9. Each bed will be visually inspected in conjunction with the sampling in Specification 3.7.8.2.b to assure that no flow blockage has occurred.
Amenhent No. JH.J H 153 3.7-15
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i DAEC-1
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LIMITING CONDITION FOR OPERATION SURVEILLANCER@lREMENT l
l 2.a The results of the inplace cold 2.a The tests and sample analysis DOP and halogenated hydrocarbon of Specification 3.7.B.2 shall tests in the flow range of 3600-be perfomed initially and then 4000 cfm on !! EPA filters and annually for standby service or l
charcoal adsorber banks shall after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system show > 99.9% 00P removal and operation and following
> 99.Y% halogenated hydrocarbon significant painting, fire or 1
- removal, chemical release in any ventila-i tion zone comunicating with the l
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system.
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- b. The results of laboratory carbon
- b. Cold DOP testing shall be sample analysis shall show < 1.0%
perfomed after e6ch complete 4
penetration of radioactive methyl or partial replacement of the i
j, iodide at 70% R.H., 150'F.
HEPA filter bank or after any i
i 40 + 4 FPM face velocity with an structural maintenance on the
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l inlet concentration of 0.5 to 1.5 systen housing, j
mg/m3 inlet concentration methyl 1
iodide.
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- c. Fans shall be shown to be capable
- c. Halogenated hydrocarbon testing i
of operation from 1800 cfm to the shall be perfomed after eacn 1
flow range of 3600-4000 cfm.
complete or partial replacement of the charcoal adsorber bank or j
af ter any structural maintenance 1
on the system housing, f
a j
- d. Each circuit shall be operated i
with the heaters on at least 10 i
j hours every month.
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3.
From and after the date that one 3.
When one train of the standby
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train cf the standby gas treat-gas treatment system becomes ment system is made or found to inoperable, the OPERABLE train l
be inoperable, reactor operation shall be demonstrated to be 4
I or fuel handling is pemissible OPERABLE imediately and daily only during the succeeding seven thereafter.
days unless such train is sooner q
made OPERABLE. provided that during such seven days all active components of the other standby gas treatment train are OPERABLE.
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4.
If Specifications 3.7.B.1, 3.7.B.2 and 3.7.B.3 are not met, the reactor shall be placed in the COLD SHUTOOWN condition h
I within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and fuel 1
I handling operations shail be l
prohibited.
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Amendment No. 78.H3.H5.153 3.7-16
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DAEC 1 needed to cleanup the reactor building atmosphere upon containment
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i isolation.
If one system is made or found to be inoperable during reactor operation or core alterai, ions, there is no imediate threat to the containment system perfomance. Thus, reactor or refueling operation (s)maycontinuewhilerepairsarebeingmade,provided l
l the requirements of Specifications 3.7.B.3 and 3.9.D. respectively, i
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are met.
If neither circuit is operable, the plant is brought to a j
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condition where the standby gas treatment system is not required.
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High efficiency particulate absolute (HEPA) filters are installed before and after the charcoal adsorbers to minimize potential
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l release of particulates to the environment and to prevent clogging i
j of the iodine adsorbers. The charcoal adsorbers are installed to 1
reduce the potential release of radiniodine to the environment.
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The in-ploce test results should indicate a system leak tightness 1
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of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99.9 percent removal of DOP particulates.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of 6t least
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99.9 percent for expected accident conditions.
If the efficiencies 1
j of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the 10 CFR 100 guidelines for I
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j Amendment No. 18,153 3.7-43
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f DAEC-1 1
i Demonstration of the automatic initiation capability and operability I
i of filter cooling is necessary to assure system perfonnance capability.
1 If one standby gas treatment system is inoperable, the other system l
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(excluding the supporting diesel generator) must be tested daily.
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t This substantiates the availability of the operable system and thus l
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reactor or refueling operation can continue fcr a limited period of l
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time.
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Initiating reactor building isolation and operation of the standby gas I
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l treatment system to maintain at least a 1/4 inch of water vacuum l
within the secondary containment provides an adequate test of the j
operation of the reactor building isolation valves, leaktightness of the reactor building and perfornutnce of the standby gav treatnent
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]i system.
Functionally testing the initiating sensors and associated
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trip channels demonstrates thi capability for automatic actuation, j
Perfoming these tests prior to refueling will demonstrate secondary I
l containment capability prior to the time the primary containment is
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opened for refueling.
Periodic testing gives sufficient t.onfidence of reactor buildir.; integrity and standby gas treatmer,t system perfonnance capability.
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l 8.
Primary Containment Power Operated Isolation Valves Automatic isolation valves are provided on process piping which l
penetrates the containment and consnunicates with the containment 4
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Amendment No, n,153 3.7-46
DAEC-1 f
atmosphere. The maximum clo N re times for these valves are selected l
in consideration of the design intent to c wt'.t eleased fission products following pipe breaks inside containment.
Several of the f
automatic isolation valves serve a dual role as both reactor coolant I
l pressure boundary isolation valves and containment isolation valves.
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The function of such valves on reactor coolant pressure boundary process piping which penetrates containment (except for those lines which are required to operate to mitigate the consequences of a loss-
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of-coolant accident) is to provide closure at a rate which will prevent core uncovery following pipe breaks outside primary contain-
- mont, il In order to assure that the doses that may result from a steam line j
break are within 10 CFR 100 guidelines, it is necessary that no fuel i
rod perforation results from the accident occur prior to closure of the main steam line isolation valves.
Analyses indicate the fue) i rod cladding perforations would be avoided for main ster'n valve closure times, including instrument delay, as long as 10.5 seconds.
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The test closure time limit of 5 seconds for these main steam isolation t
valves provides sufficient margin to assure that cladding perforations i
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are avoided.
Redundant valves in each line insure that isolation I
will meet the single failure criteria.
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i Arnentwnt No.153 3.7-47 t
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DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS b.
From and af ter the date that one of the two 125 volt station battery systems is made or found to be inoperable for any reason, reactor operation may continue for three days provided Specification 3.5.G is met, and repair is inmediately initiated, i
c.
From and after the date that.the 250 volt station battery system is made or found to be inoperable for any reason, the HPCI system L
shall be considered to be inoperable and the requirements of Specification 3.5.0 shall be met.
3.
Offsite Power 3.
Offrite Power a.
From and after the date that the a.
When it is determined that one of startup or standby transformer the diesel-generators or and one diesel-generator or associated buses is inoperable, associated buses are made or the requirements of Specification found to be inoperable for any 4.5.G.1 shall be satisfied.
reason, reactor operation may continue provided the require-ments of Specification 3.5.G.1 are satisfied.
b.
From and after the date that b.
When it is determined that both both the startup and standby the startup and standby trans-transformers become inoperable, formers are inoperable both reactor operation may continue diesel-generators, associated for seven days provided both buses and all low pressure core emergency diesel-generators, and containment cooling systems associated buses and all low shall be demonstrated to be pressure cooling systems are operable inmediately and daily operable.
thereafter.
4.
Auxiliary Electrical Equipment -
Refer to Specification 3.9.D.
Amendment No.153 3.8-4
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s DAEC-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENT D.
AUXILIARY ELECTRICAL EQUIPMENT -
CORE ALTERATI0flS shall not be performed unless all of the following conditions are satisfied:
- a. At least one off-site power source and either the startup or standby transformers are OPERABLE and capable of supplying power to the 4kV emergency buses, and
- b. One diesel-generator is OPERABLE with:
1) its associated standby gas treatment system train OPERABLE, and 2) its associated main control room ventilation standby filter unit subsysten OPERABLE.
1 Amendment No.153 3.9-4a
n-a DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.10 ADDITIONAL SAFETY RELATED PLANT 4.10 ADDITIONAL SAFETY RELATED PLANT CAPABILITIES CAPABILITIES Applicability:
Applicability:
Applies to the operating status Applies to the surveillance of the main control room ventila-requirements for the main control l
tion standby filter unit system room ventilation standby filter l
and the emergency shutdown local unit system, and the emergency control panel.
shutdown control panels which are required by the corresponding Limiting Conditions for Operation.
Objective:
Objective:
To assure the availability of the To verify that operability or main control room ventilation availability under conditions l
standby filter unit system, and for which these capabilities are emergency shutdown control panels t.n essential response to station under the conditions for which abnormalities.
the capability is an essential response to station abnormalities.
A.
MAIN CONTROL ROOM VENTILATION A.
MAIN CONTROL ROOM VENTILATION 1.
Except as specified in 1.
Annually, the pressure drop across Specifications 3.9,0 and the combined HEPA filters and 3.10. A.3, the main control room charcoal adsorber banks shall be ventilation standby filter unit demonstrated to be less than system shall be OPERABLE at all 6 inches of water at system design times when SECONDARY CONTAINMENT flow rate.
INTEGRITY is required.
2.a The results of the in-place cold 2.a The tests and sample analysis of DOP and halogenated hydrocarbon Specification 3.10. A.2 shall be tests at design flows on HEPA performed initially and then filters and charcoal adsorber annually for standby service or banks shall show > 99% DOP removal after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system and > 99% halogenated hydrocarbon operation and following signifi-removal.
cant painting, fire or chemical release in any ventilation zone comunicating with the system.
I Amendment No. W,153 3.10-1 l
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.e DAEC-1 LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT b.
The results of laboratory carbon b.
Cold D0P testing shall be sample analysis shall show > 90" perfonned af ter each complete or radioactive methyl iodide removal partial replacement of the HEPA at a face velocit of 40 fpm, filter bank or after any structural 0.05 to 0.15 mg/m inlet iodide maintenance on the system housing.
concentration. > 95% R.H. and
> 125'F.
c.
System flow shall be 1000 cfm c.
Halogenated hydrocarbon testing
+ 100 cfm.
shall be performed after each complete or partial replacement of the charcoal adsorber bank or after any structural maintenance on the system housing.
d.
Each circuit shall be operated at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> every month.
3.
From and after the date that one 3.
Annually, automatic initiation of of the main control room ventila-the control room air treatment tion standby filter unit sub-system shall be demonstrated.
systems are inoperable, reactor operation or refueling operations is permissible only during the succeeding seven days unless such circuit is sooner made OPERABLE.
4.
If these conditions cannot be met, reactor shutdown shall be initiated and the reactor shall be in COLD SHUTDOWN within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for reactor operations and refueling operations shall be
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terminated immediately.
l B.
EMERGENCY SHUTOOWN CONTROL ~
B.
EMERGENCY SHUTDOWN LOCAL CONTROL FAhEL PANEL
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At all times when not in use or 1.
The emergency shutdown local being maintained the emergency control panel shall be visually shutdown local control panel checked once per week to verify shall be secured.
it is secured.
2.
Operability of the switches on the emergency shutdown local control panel shall be func-1 tionally tested once per operating cycle.
1 Amendment No. H3.153 3.10-2
DAEC-1 filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR Part 50.
Operation of the fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If one of the systems is found to be inoperable, the second unit provides protection and reactor operation or refueling operation (s) may be performed for a limited period of time while repairs are being made.
If the system cannot be repaired within seven days, the reactor is shutdown and brought to cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or refueling operations are terminated.
1 E.
EMERGENCY SHUTDOWN LOCAL CONTROL PANEL The Emergency Shutdown Local Control Panel is provided to assure the capability of controlling reactor pressure for taking the plant to the hot shutdown condition external to the control room for the unlikely condition that the control room becomes uninhabitable.
l Amendment No.153 3.10-4
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