ML20006E739
| ML20006E739 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/14/1990 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006E740 | List: |
| References | |
| NUDOCS 9002260299 | |
| Download: ML20006E739 (10) | |
Text
_ _ _ - - - - -...
gt
,e
' [p3 RIG 4 s
4 o
UNITED STATES y l C-y" r',;n NUCLEAR REGULATORY COMMISSION
[k
[$
- WASHINGTON, D. C. 20555 l
\\.y 7 /
DUKE POWEP. COMPAhY
~
DOCKET NO. 50-369 McGUIRE NUCLEAR STATION.- UNIT 1 AMEf0 MENT TO FACILITY OPERATING LICENSE-Amendaent No. o 103 License No, hPF l'.
The Nuclear Regulatory Comission (the Comission) has found that:
A.-
The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-9 filed-e by :the Duke Power Company (the limnsee) dated October 30,.1989, complies with' the stancards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 C a mission; C.
There is reasonable assurance (1)- that the' activities authorized by this anendment 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 set = forth in 10 CFR Chapter I; D.-
TheLissuance of this amendment will not be inimictl to the common defense and security or to the health.and safety of the public; and E.
The issuance of this amenenent~ is in accordance wit'.10 r
' ut 5' of the Commission's regulations and all' applicable requirve ts have been satisfied.
y 's 0 ',22 p
0' P
b' y
4 2 --
2.
l Accordingly,'the license is hereby amenceo by pesa changes to the Technical Specifications as. incicated in the attachment to this license amencuent, _
and Paragraph 2.C.(2) of Facility Operating License No.- NPF-9 is hereby amenoed to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised' through-Amendaent No.103, are bereby incorporated into the license.
2 The licensee shall operate the facility in accordance with the Technical-Specifications and the -Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuai ce.
FOR THE flVCLEAR REGULATORY COMMISSION
?
. /I
-<</t/
David B. Matthews, Director Project Di rectorate II-3 Division of Reactor Projects-1/II Office of huclear Reactor Regulation Attachrent:
Technical Specification Changes i
/
Date of-Issuance: _ February 14, 1990
- n.
- ^..
f4
.~
1 1.'
. ;I* f
-E
~
'o, -
UNITED STATES
[p arc o
- (
NUCLEAR REGULATORY COMMISSION gi p
E
. WASHINGTON, D. C. 20555 S
%;,......f 00KE POWER COMPANY 0,0CKgj0_. 50-370 McGUIRE NUCLEAR STATION. LHIT 2 AMENDMENT TO FACILITY OPERATING LICENSE R
g Amendment No. 85 License No. NPF-17 1.
The Nuclear Regulatory Comission (the Con 1 mission)-has found that:
The app (lication for amendment to the McGuire Nuclear. Station, Unit 2-A.
by-_the Duke Power Company -(the licensee) cated October 30.:1989, t{
complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations as set forth in 10 CFR Chapter I;
'I B.
The facility will operate in conformity with the application, a
the provisions of the Act, and the rules and regulations j
of the Comission; j
C.
.There is reasonable assurance (i) that the activities authorized by j
this anendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted.
j in compliance with the Counission's: regulations set forth~ in 10 CFR-i Chapter I; j
~
-0.
The issuance of this anendment will not be inimical to the common defense ano security or to the health and safety of the public; and E.
The issuance of this amenoment is in accordance with 10 CFR 'Part 51 of the Connission's regulations and all applicable requirerents have been ~
satisfied.
j t
-I J
t 1
> h
],
3
7 g i~-
a i.
~
t'.
M.
i c-2 1.-
2.
Accordingly, the license-is herehy anended by page changes to the Technical Specifications as indicated in the attachpent to this license amenoment, and Paragr6ph 2.C.(2) of facility Operating _ Lisa,se ho. NPF-17' is hereby 1
s anended to read as follows:
Technical Specifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No 85, are hereby incorporated into the license.
The licensee shall operate the facility in accordance with the j
Technical Specifications and the Environnental Protection Plan.
3.-
This license amendment is effective as of its date of issuance.
1 FOR THE NUCLEAR REGULATORY COMMISSION i
o
/
c+/t/
David B. Matthews, Director Project Directorate II-3 Division of Reactor Projects-I/II Office of fluclear Reactor Regulation Attachre nt: -
Technical Specification Changes Date offIssuance:
February 14, 1990 1
.msdom L
1 i
i
ATTACHMENT TO LICENSE AMENDMENT-NO.10J
[ACILITY OPERATING LICENSE NO. NFF-9
. DOCKET NO. 50-369-TO LICENSE AMENDMENT NO. 85 -
FACILITY OPERATING LICENSE NO. hPF-17 DOCKET NO. 50-370 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identifieo by Anendment number and contain vertical lines indicating the areas of change.. The corresponding _ over-leaf pages are also provided to maintain document completeness.
Amended _Page Overleaf Fage 3/4 9-10 3/4 9 -3/4 9-11 3/4 9-12 0 3/4 9-2 B 3/4 9-1 p
u l:
l-l l
l l
l-1 L
(
x
~
. 1:. >
3
)
. REFUELING OPERATIONS L
L J
l Extreme of Main Hook
-y i
I i
l 1
O l
/
)
l o
Vjl v>
r W
[
7 o.
^
9
/
l e
i l
N gi 8
q.
q, 50 Af 4,
- , ih -
}-
Cask Pit o
C E 4'
2'.6 ~
=
=
. 3' 0 i
jj m
=
- 9. g Fuel Pool
)
4-S.
l
=
m E
g,
/e
.9 o
z.
o
=y
/
3 9
a g
l s
l l
n g m
)
o
. _.l _ F 1' 1 %
__=
49 FIGURE 3.9-1 REQUIRED PATH FOR MOVEMENT OF TRUCK CASKS McGUIRE UNITS.1 and 2 3/4 9-9 9 Y
+
a REFUELING OPERATIONS -
3/4'9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION HIGH WATER LEVEL LIMITING CONDITION FOR OPERATION 3.9.8.1 At least one residual heat removal (RHR) loop shall be OPERABLE and in operation.*
APPLICABILITY:
MODE 6 when the water level above the top of the reactor vessel flange-is greater than or equal to 23 feet.
ACTION:
With no RHR loop OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentra-tion of the Reactor Coolant System and immediately initiate corrective action
.to return the required RHR loop to OPERABLE and operating status as soon as possible.
Close all containment penetrations providing direct access from the-containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, l.
. SURVEILLANCE REQUIREMENTS 4.9.8.1 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, one RHR loop shall be verified in operation and circulating reactor coolant at a flow rate:
a.
greater than or equal to 1000 gpm; and b,
sufficient to maintain the RCS temperature at less than or equal to 140 F.
k
^The RHR-loop.may be removed from operation for up to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.
McGUIRE - UNITS'1 and 2 3/4 9-10 Amendment No.103 (Unit 1)
Amendment No. 85 (Unit 2) w.-
k, REFUELINGOPF"JI.'f?J LOW WATER ' ;p3 LIMITING CONDITION FOR OPERATION 3.9.8.2 Two independent residual heat removal (RHR) loops shall be OPERABLE, and at least one RHR loop shall be in operation.*
APPLICABILITY:
MODE 6 when the water level above the top of the reactor vessel flange is less than 23 feet.
ACTION:
With less than the required RHR loops OPERABLE, immediately initiate a.
corrective action to return the required RHR loops to OPERABLE.
status, or to establish greater than or equal to 23 feet of water above the reactor vessel flange, as soon as possible, b.
With no RHR loop in operation, suspend all operatioas involving a-reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation.
Close all containment penetrations providing direct' access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVE.ILLANCE REQUIREMENTS 4.9.8.2 At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, one RHR loop shall-be verified in operation and circulating reactor coolant at a flow rate:
a.
greater than or equal to 1000 gpm; and b.
sufficient to maintain the RCS temperature at less than or equal to 140 F.
i
- Prior to initial criticality, the RHR loop may be removed from operation for up to I hour per.8-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs.
McGUIRE'- UNITS 1 and.2 3/4 9-11 Amendment No.103(Unit 1) g Amendment No. 85(Unit 2)
f p[
-REFUELING OPERAT10NS
- 3/4.9.9-WATERLEVEL-REACTORVESSEL-I LIMITING CONDITION FOR OPERATION 3.9.9 At least 23 feet of water shal' be maintained over the top of the.
reactor vessel flange.
APPLICABILITY:
During movement of fuel assemblies or control rods within the
. reactor vessel when either the fuel assemblies being moved or the fuel i
assemblies seated within the reactor vessel are irradiated.
ACTION:
With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the reactor vessel.
?
SURVEILLANCE REQUIREMENTS l-l
' 4. 9. 9 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to the start of and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter-during movement of fuel assemblies or control rods.
L McGUIRE - UNITS 1 and 2 3/4 9-12
f.: _
o:
3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 BORON CONCENTRATION The limitations on reactivity conditions during REFUELING ensure that:
(1) the reactor will remain subcritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.
These limitations are consistent with the initial conditions assumed for the boron dilution incident in the accident analyses.
The value of 0.95 or less for K,ff includes a 1% delta k/k conservative allowance for uncertainties.
Similarly, the boron concentration value of 2000 ppm or greater includes a conservative uncertainty allowance of 50 ppm boron.
3/4.9.2 INSTRUMENTATION 1
-The OPERABILITY of the Source Range Neutron Flux Monitors ensures that redundant monitoring capability is available to-detect changes'in the reactivity condition of the core.
3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short-lived fission products.
This decay time is consistent with the assumptions used in the accident analyses.
3/4.9.4 CONTAINMENT BUILDING PENETRATIONS The requirements on containment building penetration closure and OPERABILITY
-of the Reactor Building Containment Purge Exhaust System HEPA filters and charcoal'adsorbers ensure that a release of radioactive material within con-tainment will be restricted from leakage to the environment or filtered through the H[PA filters and charcoal adsorbers prior to discharge to the atmosphere.
The OPERABILITY and closure restrictions are sufficient to restrict radio -
active material release'from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.
Operation of the Reactor Building Containment Purge Exhaust System HEPA filters and charcoal adsorbers and the resulting iodine removal capacity are consistent with the assumptions of the accident analysis.
The methyl iodide penetration test criteria for the carbon samples have been made more restrictive than
-required for the assumed iodine removal in the accident analysis because the humidity to be seen by the charcoal adsorbers may be greater than 70% under normal operating conditions.
-McGUIRE - UNITS 1 and 2' B 3/4 9-1
1
(.
?
m l
' REFUELING OPERATIONS BASES 3/4.9.5 COMMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity conditions during CORE ALTERATIONS.
3/4.9.6 MANIPULATOR CRANE The OPERABILITY requirements for the manipulator cranes ensure that:
(1) manipulator cranes will be used for movement of drive rods and fuel assemblies, (2) each crane has sufficient load capacity to lift a drive rod or
' fuel assembly, and (3) the core internals and reactor vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.
3/4.9.7 -CRANE TRAVEL - SPENT FUEL STORAGE POOL BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel and control rod assembly and associated handling tool over other fuel assemblies in the storage pool ensures that in the event this load is dropped:
(1) the activity release will be limited to that contained in a single fuel' assembly, and (2) any possible distortion of fuel in the storage-racks will not result in a critical array.
This' assumption is consistent with the activity release assumed in the accident analyses.
3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION
.The requirement.that at least one residual heat removal (RHR) loop be in operation ensures that:
(1) sufficient cooling capacity is available to remove decay heat and maintain the water in the reactor vessel below 140 F as required during the REFUELING MODE, and.(2) sufficient coolant circulation is maintained through the core to minimize the effect of a boron dilution incident and prevent boron stratification.
The requirement to have two RHR loops OPERABLE when there'is less than 23 feet of water above the reactor-vessel flange ensures that a single failure of the operating RHR loop will not result in a complete loss of RHR capability.
With the reactor vessel head removed and 23 feet of water above the reactor vessel flange, a large heat sink is available for core cooling.
Thus, in the event-of a failure of the operating RHR loop, adequate time is provided to initiate emergency procedures to cool the core.
To prevent vortexing in the suction of the RHR pumps, the flow rate requirements for the RHR system were lowered from 3000 gpm to 1000 gpm.
A specific surveillance has been added to ensure the flow remains high enough to ensure the reactor coolant system temperature remains less than or equal to ~
140 degrees-F. 'The problems associated with vortexing and mid-loop operations is provided in Generic Letter 88-17, Loss of Decay Heat.
McGUIRE - UNITS 1 and 2 B 3/4 9 Amendment No.103 (Unit 1)
Amendment No. 85 (Unit 2)
_m._,_.li__
i
-