ML20202E261
| ML20202E261 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 01/05/1998 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20202E267 | List: |
| References | |
| NUDOCS 9802180110 | |
| Download: ML20202E261 (26) | |
Text
.
cao uq$*t UNITED STATES po
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NUCLEAR RECULATCRY COMMISSION
't WASHINGTON. D.C. 30MH001
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50 237 DRESDEN NUCLEAR POWER STATION. UNIT 2 s
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.164 License No. DPR 19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated September 30,1997, complies with the standards and requirernents 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; 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 compilance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and secunty 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 applicaL;d 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 19 is hereby amended to read as follows:
9002180110 900105 PDR ADOCK 05000237 P
2 (2)
Technical Soecifications i
The Technical Specifications contained in Appendix A, as revised through Amendment No. 164, are hereby incorporated 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 its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION 1
CJ p&
l
.'ohn F. Stang, P oct Manager Project Directorate ill 2 Division of Reactor Projects Ill/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
Janusry 5, 1998 f
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a mou y
t UNITED STATES
.s G
NUCLEAR RE2ULATCRY CEMMISSION I
J WASHINGTON, D.C. 40006 4 001
'49.....
COhWONWEALTH EDISON COMPANY DOCKET NO. 50 24g DRE8DFN NUCLEAR POWER STATION. UN'.T_3 AMENDMENT TO FACILITY OPERATING LICENSE Amend wor,t No. 159 License No. DPR 25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated September 30,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and tne Commission's rules and regulations set forth in 10 CFR Chapter I; B.
Tho 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 careductori 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 pubhc; 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 l
Indicated in the attachment to this license amendment and paragraph 3.B. of Facility j
Operating License No. DPR 25 is hereby amended to read as follows:
o
k 2
5.
Technical Boecifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No.159 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifiations.
3.
This license amendment is effective as of the date of Ms issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGUI.ATORY COMMISSION A
John F. Stang, roject Manager Project Directorate ill 2 DWision of Weactor Projects. lll/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
January 5, 1998 m.
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ATTACHMENT TO LICENSE AMENDMENT NOS.164 AND 159 FACILITY OPERATING LICENSE NOS. DPR 19 AND DPR 25 DOCKET NOS. 50 237 AND 50-249
)
i Revise the Appendix A Technical Specifications by removing the pages identified below ans inserting the attached pages The revised pages are identified by the captioned amendme t number and contain marginal lines indicating the area of change.
i PtEMOVE INSERT i
1 Xill Xill XXVI XXVI 19 19 3/4,12 3 3/4,12-4 B?!4.121 B3/4.121 B3/4.12 2 B3/4,12 3 l
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TABLE OF CONTENTS TOC LIMITigG CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION g
2fL11 POWER DISTRIBUTION LIMITS 3/4.11. A APLHGR............................................
3/4.11 1 3/4.11.8 TLHGR.............................................
3/4.11 2 3/4.11.C MCPR.............................................
3/4.11 3 l
3/4.11.D SLHGR.............................................
3/4.11 4 1
3/4.12 SPECIAL TEST EXCEPTIONS 3/4.12. A PRIMARY CONTAINMENT INTEGRITY.......................
3/4.12 1 j
3/4.12.B SHUTDOWN MARGIN '.)emonstrations.......................
3/4.12 2 3/4.12.C Inservice Leak and Hydroststic Testing Operation...............
3/4.12 3 l
-DRESDEN UNITS 2 & 3 Xill Amendment Nos. 164 & 159
TABLE OF CONTENTS BTOC
[
BASES SECTION g
2LL11 POWER DISTRIBUTION LIMITS 3/4.11.A A PL H G R............................................
83/4.111 3/4.11.5-TLHOR............................................
83/4.111 3/4.11.C MCPR..............................................
83/4.112 3/4.11.D SLHGR.............................................
83/4.113 2/1 12 SPECIAL TEST EXCEPTIONS 3/4.12. A PRIMARY CONTAINMENT INTEGRITY.......................
B 3/4.121 3/4.12.0 SHUTDOWN MARGIN Demonstrations.......................
B 3/4.121
- 3/4.12.C Inservice Leak and Hydroststic Testing Operation-...............
B 3/4.121 l DRESDEN UNITS 2 & 3 XXVI Amendment Nos. 164 & 159 f
. - _ _ _. _. _.,. ~. - - -. -
Definiti:ns 1.0 TABLE 12 OPERATIONAL MODES MODE SWITCH AVERAGE REACTOR MODE POSITION"8 COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature 2.STARTUP Startup/ Hot Standby Any tempervture
- 3. HOT SHUTDOWN Shutdown'"'
> 212
- F'*
l
- 4. COLD SHUTDOWN Shutdown ***'
$ 212*F
- 5. REFUELING'"
Shutdown or Refuel *
- s 140*F TABLE NOTATIONS (a) The reactor mode switch may be placed in the Run, Startup/ Hot Standby or Refuel position to test the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.
(b) The reactor mode switch may be placed in the Refuel position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.10.1.
(c) Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed.
(d) See Special Test Exceptions 3.12.A,3.12.8 and 3.12.C.
l (e) The reector modo switch may be placed in the Refuel position while a single control rod is being moved piovided the one rod out interlock is OPERABLE.
(f) When there is no fuelin the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The teactor mode switch may then be in any position or may be inoporable.
DRESDEN. UNITS 2 & 3 19 Amendment Nos. 164 & 159
_ _ - =. _. _ _ _.
SELCIAL TEST EXCEP_I,1Q&S Leak / Hydro Testing 3/4.12.C 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQUIREMENTS C.
Inservice Leak and Hydrostatic Testing C. Inservice Leak and Hydrostatic Testing Operation Operation The average reactor coolant temperature Perform the applicable surveillance j
specified in Table 12 for OPERATIONAL requirements for the required MODE 4 may be changed to "NA," and OPERATIONAL MODE 3 LCOs in operation considered not to be in accordance with the frequency of the OPERATIONAL MODE 3; and the applicable surveillance requirements.
requirements of LCO 3.6.P, " Shutdown Cooling COLD SHUTDOWN," may be suspended, to allow performance of an inservice leak or hydrostatic test provided the following OPERATIONAL MODE 3 LCOs are met:
1.
LCO 3.2.A, *lsolation Actuation", Table 3.2.A 1, Functional Unit Number 2,
" SECONDARY CONTAINMENT ISOLATION";
2.
LCO 3.7.N, " SECONDARY CONTAINMENT INTEGRITY";
3.
LCO 3.7,0, " Secondary Containment Automatic isolation Dampers"; and 4.
LCO 3.7 P. " Standby Gas Treatment System."
APPLICABILITY:
OPERATIONAL MODE 4 with average reactor coolant temperature > 212 *F.
ACTION:
With one or mote of the abos a requirements
- not met:
a Separate ACTION entry is allowed for each requirement of the LCO.
DRESDEN UNITS 2 & 3 3/4.12 3 Amendment Nos. 164 & 159
j SPECIAL TEST EXCEPTIONS Leak / Hydro Testing 3/4.12.C 3.12 LIMITING CONDITIONS FOR OPERATION 4.12 - SURVEILLANCE REQUIREMENTS 1.
Immediately enter the applicable i
ACTION of the affected LCOS, or i
j 2,
immediately suspend activities that could increase the average reactor coolant temperature or pressure, and '
reduce average reactor coolant l
temperature to 5212*F within 24 j
hours.
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Required ACTIONS to be in OPERATIONAL MODE 4 include reduce everage coolant temperature s212*F.
DRESDEN UNITS 2 & 3 3/4.12 4 Amendment Nos. 164 & 159 u.
SPECIAL TEST EXCEPTIONS B 3/4.12 -
t BASES 4
s
. 3/4.12. A 2RIMARY_CD.blIAINME>tT_]NIEGBLIY l
The requirement for PRIMARY CONTAINMENT INTEGRITY is not applicable during the period when i
open.*essel tests are being performed during the low power PHYSICS TESTS. Low power-PHYSICS TESTS during OPERATIONAL MODE 2 may be required to be performed while still mal.Wning access to the primary containment and reactor pressure vessel. Additional requirements during these tests to restrict reactor power and reactor coolant temperature provide protection against potential conditions which could require primary containment or reactor coolant 3
pressure boundary integrity.
i 3/4.12.B SHUTDOWN MARGIN Demonstrat!ons Performance of SHUTDOWN MARGIN demonstrations with the vessel head removed requires additional restrictions in order to ensure that criticality does not occur. These additional restrictions are specified in this LCO. SHUTDOWN MARGIN tests may be performed while in OPERATIONAL MODE 2 in accordance with Table 12 without meeting this Special Test Exception. For SHUTDOWN MARGIN demonstrations performed while in OPERATIONAL MODE 5, additional requirements must be met to ensure that adequate protection against potential reactivity excursions is available. Because multiple control rods will be withdrawn and the reactor will potentially become critical, the approved control rod withdrawal sequence must be enforced by the RWM, or must be verified by a second licensed operator or other technically qualified individual.
To provide additional protection against inadvertent criticality, control rod withdrawals that are "out of sequence", i.e., do not conform to the Banked Position Withdrawal Sequence, must be made in individual notched withdrawal mode to minimize the potential reactivity insertion associated with each movement. Because the reacter vessel head may be removed during these tests, no other CORE ALTERATION (s) may be in progress - This Special Test Exception then allows changing the Table 12 reactor mode switch position requirements to include the Startup or Hot 4
Standby position such that the SHUTDOWN MARGIN demonstrations may be performed while in -
OPERATIONAL MODE 5.
3/4.12.C inservice Leak and Hydrostatic Testina Ooeration The purpose of this Special Test Exception LCO is to allow certain reactor coolant pressure tests to be performed in OPERATIONAL MODE 4 when the metallurgical characteristics of the reactor pressure vessel (RPV) require pressure testing at temperatures > 212 *F, which normally corresponds to OPERATIONAL MODE 3.
Pressure Testing required by Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code are performed prW to startup after a refueling outage. The -
minimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T) limits required by LCO 3.6.K, " Pressure / Temperature Limits."
These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account anticipated vessel neutron fluence. With increased reactor vessel fluence over time, the minimum allowable vessel temperature increases at a given pressure. Pressure testing will eventually be required with minimum reactor coolant temperatures > 212*F.
DRESDEN UNITS 2 & 3 B 3/4.121 Amendment Nos.164 & 15g P
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SPECIAL TEST EXCEPTIONS B 3/4.12 BASES j
i
- Allowing the reactor to be considered in OPERATIONAL MODE 4 during pressure testing, when the reactor coolant temperature is >212*F, effectively provides an exception to OPERATIONAL MODE 3 requirements, including OPERABILITY of primary containment and the full complement of redundant Emergency Core Cooling Systems. Since the pressure tests are performed at low decay heat values, and near OPERATIONAL MODE 4 conditions, the stored energy in the reactor core will
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be low.- Under these conditions, the potential for f ailed fuel and a subsequent increase in coolant activity above LCO 3.6.J, " Specific Activity," limits are minimited, in addition, secondary containment will be OPERABLE, in accordance with this Special Test Exception LCO, and will be 4
capable of handling any airborne radioactivity or steam leaks that could occur during the performance of pressure testing. The required pressure testing conditions provide adequate t
assurance that the consequences of a steam leak will be conservatively bounded by the
- consequences of the postulated main steam line break outside of primary containment described in the UFSAR. Therefore, these requirements will conservatively limit radiation releases to the i
environment.
i i
in the event of a large primary system leak, the reactor vessel would rapidly depressurire, allowing the low pressure core cooling systems to operate. The capability of the low pressure coolant injection and core spray subsystems, as required in OPERATIONAL MODE 4 by LCO 3.5.8, "ECCS Shutdown," would be more than adequate to keep the core flooded under this low decay heat load condition. Minor system leaks would be detected by leakage inspections before significant inventory loss occurred.
l For the purposes of this Special Test Exception, the protection provided by normally required OPERATIONAL MODE 4 applicable LCOs, in addition to the secondary containment requirements required to be met by this Special Test Exception LCO, will ensure acceptable consequences during normal pressure test conditions and during postulated accident conditions.
Special Test Exception LCOs provide flexibility to perform certain operations by appropriately 1
modifying requirements of other LCOs. A discussion of the criteria satisfied for the other LCOs is provided in their respective Bases. Compliance with this Special Test Exception LCO is optional.
Operation at reactor coolant temperatures > 212'F cSn be in accordance with Table 12 for OPERATIONAL MODE 3 operation without meeting this Special Test Exception LCO or its ACTIONS.
l If it is desired to perform these tests while complying with this Special Test Exception LCO, then the OPERATIONAL MODE 4 applicable LCOs and specified OPERATIONAL MODE 3 LCOs must be i
met. This Special Test Exception LCO allows changing Table 12 temperature limits for i
OPERATIONAL MODE 4 to "NA" and suspent.g the requirements of LCO 3.6.P, " Shutdown Cooling COLD SHUTDOWN." The additions, requirements for secondary containment LCOs to be met will provide sufficient protection for operations at reactor coolant temperatures > 212*F for the purpose of performing pressure testing.
- This LCO allows primary containment to be open for frequent unobstructed access to perform inspections, and for outage activities on various systems to continue consistent with the DRESDEN UNITS 2 & 3 83/4.122 Amendment Nos.164 & 15g
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SPECIAL TEST EXCEPTIONS B 3/4.12 e
BASES OPERATIONAL MODE 4 applicable requirements that are P effect immediately prior to and immediately after this operation.
The OPERATIONAL MODE 4 requirements may only be modified for the performance of inservice pressure tests so that these operations can be considered as in OPERATIONAL MODE 4, even though the reactor coolant temperature is > 212'F. The edditional requirement for secondary containment OPERABILITY sccording to the imposed OPERATIONAL MODE 3 requirements provides conservatism in the response of the unit to any event that may occur. Operations in all other OPERATIONAL MODES are unaffected by this LCO.
Footnote (a) has been provided to modify the ACTION related to pressure testing operation.
Footnote (a) allows a :parate condition entry for each requirsment of the LCO.
~
if an LCO specified in LCO 3.12.C is not met, the ACTIONS applicable io the stated requirements are entered immediately. ACTION 1 has been modified by Footnote (b) that clarifies the intent of another LCO's ACTION to be in OPERATIONAL MODE 4 which includes reducing the average reactor coolant temperature to $212'F.
ACTION 2 is an alternate action that can be taken instead of ACTION 1 to restore compliance with the normal OPERATIONAL MODE 4 requirements, and thereby exit this Special Test Exception LCO's Applicebility. Activities that could further increase reactor coolant temperature or pressure 1
are suspenha immediately, in accordance with ACTION 2, and the reactor coolant temperature is reduced tr establish normal OPERATIONAL MODE 4 requirements. The allowed completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tor ACTION 2 provides sufficient time to reduce the average reactor coolant temperature from the highest expected value to 5212'F with ncrmal cooldown procedures. The completion time is also consistent with the time provided in LCO 3.0.C to reach OPERATIONAL MODE 4 from OPERATIONAL MODE 3.
l The applicable LCOs are required to have their Surveillances met to establish that this LCO is being met. A discussion of the applicable Surveillance Requirements is provided in their respective i
l Bases.
l i
DRESDEN UNITS 2 & 3 83/4.123 Amendment Nos.164 & 15g s
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UNITED STATES g
NUCLEAR REQULATORY COMMISSION l
g WAsMINef oN, D.c, SteeHret e....
COMMONWEALTH EDISON COMPANY AND i
MIDAMERICAN ENERGY COMPANY j
f DOCKET NO. 50 254 QUAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendn.ent No, 179 License No. DPR 2g i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated September 30, igg 7, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
C, There is reasonable assurance (i) that the activities authorized by this -
amendment can be conducted without endangering the health and safety of the 3
public, and (ii) that such activities will be conducted in compliance with the I
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 1.
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.
1 2,
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR 2g is hereby amended to read as follows:
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2 B.
Technical Specifications The Technical Spedfiestions contained in Appendices A and B, as revised through Amendment No.179. are hereby incorporated 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 its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION p
obert ulsifer, P ct Manager Project Directorate Ill.2 Division of Reactor Projects til/IV office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
January 5. 1998
em to4,9 k
UNITED STATES p*
g NUCLEAR REEULATCRY CEMMISSISN wAsmwetow, p.c. asses.een essee COMMONWEALTH EDIS0N COMPANY m
1 MIDAMERICAN ENERGY COMPANY i
DOCKET NO. 80 265 QUAD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 177 L'conse No. DPR 30
-1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the i
licensee) dated September 30,1997, 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 hatth 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, t
2.
~ Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR 30 is hereby amended to read as follows:
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Technical Boecifications The Technical Specifications contained in Appendices A and B, as revised throuph Amendment No.177, are hereby incorporated in the license. Ti.e licensee shall operate the facility in accordance with the Technical Spcoifications, 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION d4 Robert M. PulsiferfProject Manager Project Directorate lil 2 Division of Reactor Projects. Ill/lV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of lasuance:
January 5, 1996
ATTACHMENT TO LICENSE AMEijoMENT NOS. 179 AND 177 FACILITY OPERATING LICENSU NOS. OPR 29 AND DPR 30 DOCKET NOS. 50 254 AND 50-265 Revise the Appendix A Technical SpecMications by removing the pages identified below and inserting the attached pages. The revised pagts tre identified by the captioned amendment s
number and contain marginallinea indicating the sea of change.
REMOVE INSERT g
Xill Xlll XXVI XXVI 19 19 3/4.12-3 3/4.12-4 B3/4.12-1 B3/4.121 B3/4.12 2 83/4.12-3 t-i
TABLE OF CONTENTS TOC s
LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION EAJE 3/4.11 POWER DISTRIBUTION LIMITS
]
3/4.11.A APLHGR............................................
3/4.11-1 3/4.11.B TLHGR.............................................
3/4.11-2 3/4.11.C MCPR..............................................
3/4.11-4 3/4.11.D LHGR..............................................
3/4.11 5 3/4.12 SPECit.L TEST EXCEPTIONS 3/4.12. A PRIMARY CONTAINMENT INTEGRITY,......................
3/4.12-1 3/4.12.B SHUTDOWN MARGIN Demonstrations.......................
3/4.12-2 3/4.12.C Inservice Leak and Hydrostatic Testing Operation...............
3/4.12-3 l QUAD CITIES - UNITS 1 & 2 Xill Amendment Nos. 179 & 177
TABLE OF CONTENTS B TOC s
BASES SECTION MGc 3/4.11 POWER DISTRIBUTIOS LIMITS 3/4.11.A A PL H G R............................................
B 3/4.11 1 3/4.11.B TLHGR.............................................
B 3/4.112 3/4.11.C MCPR..............................................
B 3/4.11-2 3/4.11.D LHGR..............................................
B 3/4.11-4 0
2 L4 1 2 SPECIAL TEST EXCEPTIONS 3/4.12. A PRIMARY CONTAINMENT INTEGRITY.......................
B 3/4.121 3/4.12.B SHUTDOWN MARGIN Demonstrations.......................
B 3/4.121 3/4.12.C Inservice Leak and Hydrostatic Testing Operation...............
B 3/4.121 l QUAD CITIES - UNITS 1 & 2 XXVI Amendment Nos. 1797. 17
Definiti:ns 1.0 s
s TABLE 12 9
OPERATIONAL MODES MODE SWITCH A'!ERAGE REACTOR MQD.E POS!TIONm COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature 2.STARTUP Startup/ Hot Standby Any temperature
- 3. HOT SHUTDOWN Shutdown'"'
> 212*F'*
l
- 4. COLD SHUTDOWN Shutdown"**'
s 212*F
- 5. REFUELING'"
Shutdown or Refuel"*
s 140*F TABLE NOTATIONS (a) The reactor mode switch may be placed in the Run, Startup/ Hot Standby or Refuel position to test the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.
(b) The reactor mode switch may be placed in the Refual position while a single control rod drive is being removed from the reactor pressure vessel per Specification 3.10,l.
(c) Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed.
(d) See Special Test Exceptions 3.12.A,3.12.B and 3.12.C.
l (e) The reactor mode switch may be placed in the Refuel position while a single control rod is being moved provided the one-rod-out interlock is OPERABLE.
(f) When there is no fuel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode switch may then be in any position or may be inoperable.
QUAD CITIES - UNITS 1 & 2 19 Amendment Nos. 179 & 177 l
~
SPECIAL TEST EXCEPTIONS Loak/ Hydro Testing 3/4.12.C 9
3.12 LIMITING CONDITIONS FOR OPERATION 4.1? - SURVEILLANCE REQUIREMENTS
-.r w_
C.
Ingervice Leak and Hydrostatic Testing C.
Inservice Leak and Hydrostatic Testing Oporation Operation The average reactor coolant temperature Perform the applicable surveillance specified in Table 12 for OPERATIONAL requirements for the required 3
MODE 4 may be changed to "NA," and OPERATIONAL MODE 3 LCOs in operation considered not to be in accordance with the frequency of the OPERATIONAL MODE 3; and the applicable surveillance requirements, requirements of LCO 3.6.P, " Residual Heat Removal COLD SHUTDOWN," may be suspended, to allow performance of en inservice leak or hydrostatic test provided E
the following OPERATIONAL MODE 3 LCOs
]
are met:
1.
LCO 3.2.A, " Isolation Actuation," Table 3.2.A 1, Functional Unit Number 2,
' SECONDARY CONTAINMENT ISOLATION";
2.
LCO 3.7.N, " SECONDARY CONTAINMENT INTEGRITY";
3.
LCO 3.7,0, " Secondary Containment Automatic isolation Dampers"; and 4.
LCO 3.7.P, " Standby Gas Treatment System."
APPLICABILITY:
OPERATIONAL MODE 4 with everage reactor coolant temperature > 212'F.
ACTION:
With one or more of the above requirements'd not met:
Separate ACTION entry is allowed for each requirement of the LCC.
a QUAD CITIES - UNITS 1 & 2 3/4.12 3 Amendment Nos. 179 & 177 l
SPECIAL TEST EXCEPTIONS Leak / Hydro Testing 3/4.12.C v
3.12 LIMITING CONDITIONS FOR OPERATION 4.12 SURVEILLANCE REQUIREMENTS 1.
Immediately enter the applicable ACTION of the affected LCO'", or 2.
Immediately suspend activities that could increase the average reactor coolant temperature or pressure, and reduce average reactor coolant temperature to s212*F wahin 24
- hours, 1
1 l
b Required ACTIONS to be in OPERATIONAL MODE 4 include reduce average coolant temperature s;212*F.
QUAD CITIES - UNITS 1 & 2 3/4.12 4 Amendment Nos. 179 & 177
SPECIAL TEST EXCEPTIONS B 3/4.12 9
BASES 3/4.12. A PRIMARY CONTAINMENT' INTEGRITY The requirement for PRIMARY CONTAINMENT INTEGRITY is not applicable during the period when open vessel tests are being performed during the low power PHYSICS TESTS. Low power PHYSICS TESTS during OPERATIONAL MODE 2 may be required to be performed while still maintaining access to the primary containment and reactor pressure vessel. Additional requirements during these tests to restrict reactor power and reactor coolant temperature provide protection againt.t potential conditions which could require primary containment or reactor coolant pressure boundary integrity.
3/4112.B SELT."OWN MARGIN Demonstrations Performance of SHUTDOWN MARGIN demonstrations with the vessel head removed requires additional restrictions in order to ensure that critical:ty does not necur. These additional restrictions are specified in th!s LCO. SHUTDOWN MARGIN tests may be performed while in OPERATIONAL MODE 2 in accordance with Table 12 without meeting this Special Test Exception. For SHUTDOWN MARGIN demonstrations performed while in OPERATIONAL MODE 5, additional requirements must be met to ensure that adequate protection against potential reactivity excursions is available.- Because multiple control rods will be withdrawn and the reactor will ptentially become critical, the approved control rod witodrawal sequence must be enforced by the R'NM, or must be verified by a second licensed operator or other technically qualified individual.
To prr, side additional protection against inadvertent criticality, control rod withdrawals that are "out of sequence", i.e., do not conform to the Banked Position _ Withdrawal Sequence, must be
- made in individual notched withdrawal mode to minimize the potential reactivity insertion associated with each movement. Because the reactor vessel head may be removed during these
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tests, ne other CORE ALTERATION (s) may be in progress. This Special Test Exception then allows changing the Table 12 reactor mode switch position requirements to include the Startup or Hot Standby position such that the SHUTDOWN MARGIN demonstrations may be performed while in OPERATIONAL MODE 5.
3/4.12.C
" Inservice Leak and Hydrostatic Testina Ocaration The purpose of this Special Test Exception LCO is to allow certain reactor coolant pressure tests to
- be performed in CPERATIONAL MODE 4 when the metallurgical characteristics of the reactor pressure vessel (RPV) require pressure testing at temperatures > 212
- F, which normally corresponds to OPFRATIONAL MODE 3.
Pressure Testing required by Section XI of the American Scciety of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code are peric med prior to startup after a refueling outage. The rrinimum temperatures (at the required pressures) allowed for these tests are determined from the RPV pressure and temperature (P/T) limits required by LCO 3.6.K, " Pressure / Temperature Limits."
These limits are conservatively based on the fracture toughness of the reactor vessel, taking into account anticipated vessel neutron fluence. With increased reactor vessel fluence over time, the minimum allowabl6 vessel temperature increases at a given pressure. Pre.ssure testing will eventually be required with minimum reactor coolant temperatures > 212 *F.
QUAD CITIES - UNITS 1 & 2 B 3/4.12-1 Amendment Nos. 179 & 177
SPECIAL TEST EXCEPTIONS B 3/4.*42 y'
BASES-Allowing the rea:: tor to be considered in OPERATIONAL MODE 4 during pmure testing, when the -
reactor coolant temperature is > 212 *F, effectively provides an exception to OPERATIONAL MODE 3 requirements, including OPERABILITY of primary containment and the full complement of rodundant Emergency Core Cooling Systems. Since the pressure tests are perforrned at low decay heat values, and near OPERATIONAL MODE 4 conditions, the stored energy in the reactor core will be low, Under these conditions, the potential for failed fuel and a subsequent increase in coolant activity above LCO 3.6.J, " Specific Activity," limits are minimized, in addition, secondary containment will be OPERABLE, in accordance with this Special Test Exception LCO, and will be capable of handling any airborne radioactivity or steam leaks that could occur during the performance of pressure testing. The required pressure testing conditions provide adequate assurance that the consequences of a steam leak will be conservatively bounded by the consequences of the postulated main steam line break outside of primary containment described in the UFSAR. Therefore, these requirements will conservatively limit radiation releases to the environment, in the event of a large primary system leak, the reactor vessel would rapidly depressurize, allowing the Bow pressure core cooling systems t1 operate. The capability of the low pressure coolant injaction and core spray subsystems, as required in OPERATIONAL MODE 4 by LCO 3.5.B, "ECCS Shutdown," would be more than adequate to keep the core flooded under this low decay heat load condition. Minor system leaks would be detected by leakage inspections before significant inventory loss occurred.
For the purposes of this Special Test Exception, the protection provided by normally required OPERATIONAL MODS 4 applicable LCOs, in addition to the secondary containment requirements required to be met b - 5is Special Test Exception LCO, will ensure acceptable consequences during i
normal pressure test wnditions and during postulated accident conditions.
Specla! Test Exception LCOs provide flexibility to perform certain operations by appropriately modifying requirements of other LCOs. A discussion of the criteria satisfied for th other LCOs is provided in their respective Bases. Compliance with this Special Test Exception LCO is optional.
Operation at reactor coolant temperatures >212*F can be in accordance with Table 1-2 for OPERATIONAL MODE 3 operation without meeting this Special Test Exception LCO or its ACTIONS.
If it is desired to perform these tests while complying with this Special Test Exception LCO, then the OPERATIONAL MODE 4 applicable LCOs and specified OPERATIONAL MODE 3 LCOs must be met. This Special Test Exception LCO allows changing Table 12 temperature limits for OPERATIONAL MODE 4 to "NA" and suspending the requirements of LCO 3.6.P. " Residual Heat Removal COLD SHUTDOWN." The additional requirements for secondary containment LCOs to be met will provide sufficient protection for operations at reactor coolant temperatures > 212 *F for the purpose of performing pressure testing.
This LCO allows primary containment to be open for frequent unobstructed access to perform inspections, and for outage activities on various systems to continue consistent with the QUAD CITIES - UNITS 1 & 2 B 3/4.12-2 Amendment Nos. 179 & 177 i
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SPECIAL TEST EXCEPTIONS B 3/4.12 6
BASES OPERATIOt!AL MODE 4 applicable requirements that are in effect immediately prior to and immediately efter this operation.
g The OPERATIONAL MODE 4 requirements may only be modified for the performance of inservice pressure tests so that these operations can be considered as in OPERATIONAL MODE 4, even though the reactor coolant temperature is >212*F. The additional requirement for secondary containment OPERABILITY according to the imposed OPERATIONAL MODE 3 requirements provides conservatism in the response of the unit to any event that may occur. Operations in al' other OPERATIONAL MODES are unaffected by this LCO.
g Footnote (a) has been provided to modify the ACTIONS related to pressure testing operation.
Footnote (a) allows a separate condition entry for each requirement of the LCO.
If an LCO specified in LCO 3.12.C is not met, the ACTIONS applicable to the stated requirements are entered immediately. ACTION 1 has been modified by Footnote (b) that clarifies the intent of another LCO's ACTION to be in OPERATIONAL MODE 4 which includes reducing the average reactor coolant temperature to 5212*F.
ACTION 2 is an alternate action that can be taken instead of ACTION 1 to restore compliance with the normal OPERATIONAL MODE 4 requirements, and thereby exit this Special Test Exception LCO's Applicability. Activities that could further increase reactor coolant temperature or pressure are suspended immediately, in accordance with ACTION 2, and the reactor coolant temperature is reduced to establish normal OPERATIONAL MODE 4 requirements. The allowed completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for ACTION 2 provides sufficient time to reduce the average reactor coolant temperature from the highest expected value to s212 *F with normal cooldown procedures. The completion time is also consistent with the time arovided in LCO 3.0.C to reach OPERATIONAL MODE 4 from OPERATIONAL MODE 3.
The applicable LC,0s are required to have their Surveillances met to establ:sh that this LCO is being met. A discuscion of the applicable Surveillance Requirements is provided in their respective Bases.
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OUAD CITIES - UNITS 1 & 2 B 3/4.12-3 Amendment Nos. 179 & 177
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