ML20069N478
| ML20069N478 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 06/16/1994 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20069N482 | List: |
| References | |
| NUDOCS 9406220423 | |
| Download: ML20069N478 (38) | |
Text
1 pa ctav 80 UNITED STATES 4
l
]
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001 COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT'TO FACILITY OPERATING LICENSE Amendment No. 127 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 March 26, 1993, 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; C.
There is reasonable assurance (1) 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 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.
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-19.is hereby amended to read as follows:
9406220423 940616 PDR ADOCK 05000237 P
7
[-
1{
. (2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.127, 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.
FOR THE NUCLEAR REGULATORY COMMISSION Rasa.C u Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects -
III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 16, 1994
ATTACHMENT TO LICENSE AMENDMENT NO. 127 FACILITY OPERATING LICENSE NO. DPR-19 DOCKET N0. 50-237 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
l REMOVE INSERT viii viii 3/4.6-13 3/4.6-13 3/4.6-14 3/4.6-14 3/4.6-15 3/4.6-15 3/4.6-16 3/4.6-16 3/4.6-24 3/4.6-24 B 3/4.6-36 8 3/4.6-36 l
B 3/4.6-37 B 3/4.6-37 I
l l
r l
1 l
DRESDEN II DPR-19 Amendment No 127 List of Tables (continued)
P_A91 Table 3.12-1 Deleted Table 3.12-2 Deleted i
Table 3.12-3 Deleted Table 3.12-4 Deleted Table 6.1.1 Minimum Shift Manning Chart 6-4 Table 6.6.1 Special Reports 6-23 List of Fiaures l
l Figure 2.1-3 APRM Bias Scram Relationship to Normal B 1/2.1-17 l
Operating Conditions l
Figure 4.1.1 Graphical Aid in the Selection of B 3/4.1-18 an Adequate Interval Between Tests l
Figure 4.2.2 Test Interval vs System Unavailability B 3/4.2-38 Figure 3.4.1 Deleted 3/4.4-4 Figure 3.4.2 Sodium Pentaborate Solution Temperature 3/4.4-5 Requirements Figure 3.6.1 Minimum Reactor Vessel Metal Temperature 3/4.6-23 Figure 3.6.2 Deleted 3/4.6-24 l
Figure 4.6.1 Minimum Reactor Pressurization Temperature B 3/4.6-29 Figure 4.6.2 Chloride Stress Corrosion Test Results at 500*F B 3/4.6-31 Figure 4.8.1 Owner Controlled / Unrestricted Area Boundary B 3/4.8-38 Figure 4.8.2 Detail of Central Complex B 3/4.8-39 Figure 6.1-1 Offsite Organization - Deleted i
Figure 6.1-2 Station Organization - Deleted viii
i DRESDEN II DPR-19 Amendment No. 127 j
j 4
THIS PAGE INTENTIONALLY LEFT BLANK i
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1 1
l 3/4.6-13
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+>
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/
x
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DRESDEN II DPR-19 l
Amendment No.127 l
l l
1 l
TilIS PAGE INTENTIONALLY LEFT BLANK l
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3/4,6-14 l
~l DRESDEN II DPR-19 Amendment No. 127 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE RE0VIREMENT (Cont'd.)
(Cont'd.)
3.
During Single Loop Operation 3.
Deleted 4
for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the j
following restrictions are required:
)
a.
The recirculation pump i
in the idle loop shall be electrically prohibited from starting except to permit testing in preparation for returning to service.
j i
J b.
The flow biased RBM Rod Block LSSS shall be l
reduced by 4.0%
(Specification 3.2.C.1);
l c.
The flow biased APRM Rod Block LSSS shall be reduced by 3.5%
l (Specification 2.1.8);
d.
.The flow biased APRM scram LSSS shall be reduced by 3.5%
(Specification 2.1.A.1);
e.
The MCPR Safety Limit shall be increased by 0.01 (Specification 1.1.A);
f.
The rated flow MCPR Operating Limit shall be increased by 0.01 (Specification 3.5.L.2);
3/4.6-15
!I i
DRESDEN II Amendment No.12[PR-19 3.6 LIMITING CONDITION FOR OPERATION 4.6 SVRVEILLANCE REQUIREMENT l
(Cont'd.)
(Cont'd.)
g.
The MAPLHGR Operating Limit shall be reduced 4
l by the appropriate multiplicative factor from the Core Operating i
Limits Report (Specification 3.5.1).
]
If concurrently one AutomaticPressur,e i
Relief Subsystem relief valve is out-of-service, the MAPLHGR Operating j
Limit shall be reduced by the appropriate i
multiplicative factor from the Core Operating i
Limits Report.
4 4.
With-no reactor. coolant system recirculation loops -in operation reduce core thermal i
powertolessthan25%ofrated i
within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and place the unit in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
Idle Recirculation Loop Startup 5.
Idle Recirculation Loop Startup i
An idle recirculation pump shall The temperature differentials and flow not be started unless the rates shall be determined to be within j
temperature differential between the limits within 15 minutes prior to the reactor vessel steam space startup of an idle recirculation loop.
j coolant and the bottom head a'
drain line coolant is less than or equal to 145'F*, and:
Whenbothpumkhetemperature s have been a.
idle unless diffe,rential between the 1
reactor coolant within the i
idle loop to be started up and the coolant in the reactor pressure vessel is c
less than or equal to 50'F, or 4
i I
b.
When only one loop has been l
1 idle unless the temperature diffe,rential between the
]
reactor coolant within the j
idle and operating recirculation loops is less than or equal to 50*F and the speed of the operating is less than or equal pump % of rated pump speed.
i to 43 i
I 1.
Snubbers (Shock Suppressors)
I.
Snubbers (Shock Suppressors)
The following surveillance requirements apply to safety related 4
1
]
- 0nly applicable with reactor pressure vessel steam space pressure ;t 25 psig.
i 3/4.6-16 a
t, DRESDEN II DPR-19 Amendment No. 127 t
THIS PAGE WAS LEFT INTENTIONALLY BLANK I
l 3/4.6-24
DRESDEN II DPR-19 Amendment No.127 3.6 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)
l The decrease of the MAPLHGR Operating Limit by the multiplicative factor specified in the Core Operating Limits Report accounts for the more rapid loss of core flow l
during Single Loop Operation than during Dual Loop Operation.
I The more conservative MAPLHGR reduction factors in the Core Operating Limits Report are applied if one relief and one recirculation loop are inoperable at the same time. The small break LOCA is the concern for one relief valve out-of-service; the large break LOCA is the concern for Single Loop Operation.
Selecting the more conservative MAPLHGR multipliers will cover both the relief valve out-of-service and i
l Single Loop Operation.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperature shall be within 50*F of each other prior to startup of an idle loop. The loop temperature must also be within 50*F of the reactor pressure vessel steam space coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles.
Since the coolant in the bottom of the vessel is at a lower temperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the temperature difference were greater than 145'F. Additionally asymmetric speed operation of recirculation. umps during idle loop startup induces levels of jet pump riser vibration that are hi her than normal. The specific limitation of 43% of rated pump speed for the operat ng recirculation pump prior to the start of the idle recirculation pump ensures that the recirculation pump speed mismatch requirements presented in Specification 3.6.H.1 as well as the margin to the MCPR Fuel Integrity Safety Limit are maintained.
I.
Snubbers (Shock Sucoressors)
Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient while allowing normal thermal l
motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of a seismic or other event initiating dynamic loads.
It is therefore required that all snubbers i
required to protect the primary coolant system or any other safety system or l
component be operable during reactor operation.
l Because the snubber protection is required only during low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
In case a shutdown is i
required the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition will permit anorderlyshutdownconsistentwithstandardoperatingprocedures.
Since plant startup should not commence with knowingly defective safety-related equipment, Specification 3.6.I.4 prohibits startup with inoperable snubbers.
l When a snubber is found inoperable, a review shall be performed to determine the l
snubber mode of failure.
Results of the review shall be used to determine if an engineering evaluation of the safety-related system or component is necessary.
The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the support component or system.
All safety-related hydraulic snubbers are visually inspected for overall integrity and operability. The inspection will include verification of proper orientation, adequate hydraulic fluid level and proper attachment of snubber to piping and structures.
All safety-related mechanical snubbers are visually inspected for overall integrity and operability.
The inspection will include verification of proper orientation and attachments to the piping and anchor for indication of damage or impaired operability.
3/4.6-37
1 4
i DRESDEN II DPR-19 Amendmant No.127 i
3.6 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)
4 In addition, during the start-up of Dresden, Unit 2, it was found that a flow mismatch between the two sets of jet pumps caused by a difference in recirculation loops could set up a vibration until a mismatch in speed of 27% occurred. The 10%
)
]
and 15% speed mismatch restrictions provide additional margin before a pump vibration problem will occur.
l 4
Analyses have been performed which support indefinite operation in single loop provided the restrictions discussed in Specification 3.6.H.3 are implemented within l
l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a The LSSSs are corrected to account for backflow through the idle jet pumps above 20-4 40% of rated recirculation pump speed. This assures that the original drive flow i
biased rod block and scram trip settings are preserved during Single Loop Operation.
The MCPR safety limit has been increased by 0.01 to account for core flow and TIP 3
reading uncertainties which are used in the statistical analysis of the safety limit.
In addition, the rated flow MCPR Operating Limit has also been increascd by 0.01 to maintain the same margin to the safety limit as during Dual Loop Operation.
)
During single loop operation for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the idle recirculation pump is electrically prohibited from starting until ready to resume two loop operation.
This is done to prevent a cold water injection transient caused by an inadvertent j
pump startup.
i a
i i
l t
B 3/4.6-36
sG MGu y.~
4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON, D.C. 20566-0001 k...../
COMMONWEALTH EDIS0N COMPANY l
DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 121 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 March 26, 1993, 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; 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
r 1
1-
'l
. 'i B.
Technical Specifications l
The Technical Specifications contained in Appendix A,. as revised i
l through Amendment No.121, are hereby inco'rporated in the license.
The-licensee shall operate the facility in accordance :with the 1
Technical Specifications.
1 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
' <Wo. C'w Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 16, 1994 l
l.
t g-y
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,n2
- a i
g
--yw-*r 1+u.--
- ----i
I ATTACHMENT TO LICENSE AMENDMENT NO. 121 FACILITY OPERATING LICENSE NO. DPR-25
~
DOCKET N0. 50-249 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment-number and contain marginal lines indicating the area of change.
REMOVE INSERT
\\
l viii viii 3/4.6-13 3/4.6-13 3/4.6-14 3/4.6-14 3/4.6-15 3/4.6-15 j
3/4.6-16 3/4.6-16 3/4.6-24 3/4.6-24 B 3/4.6-36 B 3/4.6-36 i
B 3/4.6-37 B 3/4.6-37
DRESDEN III DPR-25 Amendment No.
121 List of Tables (continued)
P19%
Table 3.12-2 Deleted Table 3.12-3 Deleted Table 3.12-4 Deleted Table 6.1.1 Minimum Shift Manning Chart 6-4 Table 6.6.1 Special Reports 6-22 List of Fiaures l
Figure 2.1-3 APRM Bias Scram Relationship to Normal B 1/2.1-17 r
Operating Conditions Figure 4.1.1 Graphical Aid in the Selection of B 3/4.1-18 an Adequate Interval Between Tests Figure 4.2.2 Test Interval vs System Unavailability B 3/4.2-38 Figure 3.4.1 Deleted 3/4.4-4 Figure 3.4.2 Sodium Pentaborate Solution Temperature 3/4.4-5 Requirements Figure 3.6.1 Minimum Reactor Vessel Metal Temperature 3/4.6-23 l
Figure 3.6.2 Deleted 3/4.6-24
)
Figure 4.6.1 Minimum Reactor Pressurization Temperature B 3/4.6-29 Figure 4.6.2 Chloride Stress Corrosion Test Results at 500*F B 3/4.6-31 Figure 4.8.1 Owner Controlled / Unrestricted Area Boundary B 3/4.8-38 Figure 4.8.2 Detail of Central Complex B 3/4.8-39 Figure 6.1-1 Offsite Organization - Deleted Figure 6.1-2 Station Organization - Deleted viii
t
~
DRESDEN III DPR-25 Amendment No. 121 i
l I
THIS PAGE INTENTIONALLY LEFT BLANK 3/4.6-13
d DRESDEN III OPR-25 Amendment No. 121 i,
t M
THIS PAGE INTENTIONALLY LEFT BLANK 1
4 4
'b e.
L 3/4.6-14 I
i
~
i i
DRESDEN III DPR-25 l
Amendment No. 121 3.6 LIMITING CONDITION FOR OPERATION 4.6 SURVEILLANCE REQUIREMENT (Cont'd.)
(Cont'd.)
3.
During Single Loop Operation 3.
Deleted for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the following restrictions are required:
a.
The recirculation pump in the idle loop shall be electrically prohibited from starting l
except to permit testing in preparation for returning to service, b.
The flow biased RBM Rod Block LSSS shall be reduced by 4.0%
(Specification 3.2.C.1);
c.
The flow biased APRM Rod Block LSSS shall be reduced by 3.5%
(Specification 2.1.B);
d.
The flow biased APRM scram LSSS shall be reduced by 3.5%
(Specification 2.1. A.1);
e.
The MCPR Safety Limit shall be increased by 0.01 (Specification 1.1.A);
f.
The rated flow MCPR l
Operating Limit shall be increased by 0.01 (Specification 3.5.L 2);
I l
3/4.6-15 1
i d
ORESDEN III DPR-25 Amendment No. 121 3.6 LIMITD G CONDITION FOR OPERATION 4.6 SURVEILLANCE RE0VIREMENT (Cont'c. )
(Cont'd.)
l g.
The MAPLHGR Operating Limit shall be reduced by the appropriate multiplicative factor from the Core Operating i
i Limits Report (Specification 3.5.I).
If concurrently, one Aufomatic Pressure Relief Subsystem relief valve is out-of-service, the MAPLHGR Operating Limit shall be reduced by the appropriate multiplicative factor Limits Report. perating from the Core O 4.
With no reactor coolant system recirculation loops in operation reduce core thermal powertolessthan25%ofrated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and place the unit in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
Idle Recirculation Loop Startup 5.
Idle Recirculation Loop Startup An idle recirculation pump shall The temperature differentials and flow not be started unless the rates shall be determined to be within temperature differential between the limits within 15 minutes prior to the reactor vessel steam space startup of an idle recirculation loop.
coolant and the bottom head drain line coolant is less than or equal to 145'F*, and:
a.
When both pumps have been idle, unless the temperature differential between the reactor coolant within the idle loop to be started up and the coolant in the reactor pressure vessel is less than or equal to 50*F, or b.
When onlY one loop has been idle unless the temperature diffe,rential between the reactor coolant within the idle and operating recirculation loops is less than or equal to 50*F and the speed of the operating is less than or equal pump % of rated pump speed.
to 43 I.
Snubbers (Shock Suppressors)
I.
Snubbers (Shock Suppressors)
The following surveillance requirements apply to safety related snubbers.
- 0nly applicable with reactor pressure vessel steam space pressure 2 25 psig.
3/4.6-16
i 1'
DRESDEN III DPR-25 Amendment No. 121 i
1 i
THIS PAGE WAS LEFT INTENTI0MALLY BLANK
-l I
l I
l l
l 3/4.6-24
~. _..
7' DRESDEN III DPR-25 Amendment No. 121 l
3.6 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)
In additien, during the start-up of Dresden, Unit 2, it was found that a flow mismatch between the two sets of jet pumps caused by a difference in recirculation loops could set up a vibration until a mismatch in speed of 27% occurred.
The 10%
l and 15% speed mismatch restrictions provide additional margin before a pump vibration problem will occur.
i l
Analyses have been performed which support indefinite operation in single loop i
i provided the restrictions discussed in Specification 3.6.H.3 are implemented within
~
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I The LSSSs are corrected to account for backflow through the idle jet pumps above 20-40% of rated recirculation pump speed. This assures that the original drive flow 3
biased rod block and scram trip settings are preserved during Single Loop Operation.
i The MCPR safety limit has been increased by 0.01 to account for core flow and TIP reading uncertainties which are used in the statistical analysis of the safety limit.
In addition, the rated flow MCPR Operating Limit has also been increased by 0.01 to maintain the same margin to the safety limit as during Dual Loop Operation.
During single loop operation for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the idle recirculation pump i
is electrically prohibited from starting until ready to resume two loop operation.
This is done to prevent a cold water injection transient caused by an inadvertent pump startup.
i j
I I
i l
4 i
j i
B 3/4.6-36 4
DRESDEN III DPR-25 Amendment No. 121 l
3.6 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)
The decrease of
- MAPLHGR Operating Limit by the multiplicative factor specified in the Core Ops...., Limits Report accounts for the more rapid loss of core flow during Single Loop Operation than during Dual Loop Operation.
The more conservative MAPLHGR reduction factors in the Core Operating Limits Report are applied if one relief and one recirculation loop are inoperable at the same time. The small break LOCA is the concern for one relief valve out-of-service; the large break LOCA is the concern for Single Loop Operation.
Selecting the more conservative MAPLHGR multipliers will cover both the relief valve out-of-service and Single Loop Operation.
In order to prevent undue stress on the vessel nozzles and bottom head region, the l
l recirculation loop temperature shall be within 50'F of each other prior to startup of an idle loop.
The loop temperature must also be within 50*F of the reactor pressure vessel steam space coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles.
Since the coolant in the bottom of the vessel is at a lower temperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the temperature difference were greater than 145'F. Additionally asymmetric speed operation of recirculation umps during idle loop startup induces levels of jet pump riser vibration that are hi her than normal. The specific limitation of 43% of rated pump speed for the operat ng recirculation pump prior to the start of the idle recirculation pump ensures that the recirculation pump speed mismatch requirements presented in Specification 3.6.H.1 as well as the rurgin to the MCPR Fuel Integrity Safety Limit are maintained.
I.
Snubbers (Shock Sucoressors) l Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as l
might occur during an earthquake or severe transient while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubber is an increase in the probabilit of structural damage to piping as a result of a seismic or other event initiating ynamic loads.
It is therefore required that all snubbers required to protect the pr mary coolant system or any other safety system or component be operable during reactor operation.
Because the snubber protection is required only during low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replacements.
In case a shutdown is required the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition will permit anorderiyshutdownconsistentwithstandardoperatingprocedures.
Since plant startup should not commence with knowingly defective safety-related equipment, Specification 3.6.I.4 prohibits startup with inoperable snubbers.
When a snubber is found inoperable, a review shall be performed to determine the snubber mode of failure.
Results of the review shall be used to determine if an engineering evaluation of the safety-related system or component is necessary. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the support component or system.
All safetyility.related hydraulic snubbers are visually inspected for overall integrity and operab The inspection will include verification of proper orientation, l
adequate hydraulic fluid level and proper attachment of snubber to piping and structures.
All safety-related mechanical snubbers are visually inspected for overall integrity l
and operability.
The inspection will include verification of proper orientation and l
attachments to the piping and anchor for indication of damage or impaired operability.
3/4.6-37 l
n Geog a
[
\\
UNITED STATES j
NUCLEAR REGULATORY COMMISSION l
WASHINGTON, D.C. 20666 @ 01 l
\\...../
i COMMONWEALTH EDISON COMPANY j
MQ IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY l
DOCKET N0. 50-254 l
l OVAD CITIES NVCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.147 License No. DPR-29' 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l l
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 26, 1993, complies with the standards arid 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; l
C.
There is reasonable assurance (1) that the activities authorized -
l
)
by this amendment can be conducted without endangering the health l
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 l
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.
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-29 is hereby amended to read as follows:
. B.
Technical Soecifications j
The Technical Specifications contained in Appendices A and B, as l
revised through Amendment No. 147, are hereby incorporated in the l
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.
FOR THE NUCLEAR REGULATORY COMMISSION 0' W i
Robert A. Capra, Director
. Project Directorate III-2 Division of Reactor Projects - III/IV Office of' Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 16, 1994 l
i l
l t
1
l l
ATTACHMENT TO LICENSE AMENDMENT NO. 147 FACILITY OPERATING LICENSE NO. DPR-29 l
DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
l REMOVE INSERT 1.1/2.1-3 1.1/2.1-3 3.6/4.6-11 3.6/4.6-11 3.6/4.6-12 3.6/4.6-12 3.6/4.6-12a 3.6/4.6-24 3.6/4.6-24 3.6/4.6-24a l
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f QUAD CITIES DPR-29 3.
IRM Flux Scram Trip Setting The IRM flux scram setting shall be set at less than or equal to 120/125 of full scale.
B.
Core Thermal Power Limit (Reactor B.
APRM Rod Block Setting Pressure s 800 psig)
The APRM rod block setting shall be When the reactor pressure s 800 psig shown in Figure 2.1-1 and shall be:
or core flow is less than 10% of I
rated, the core thermal power shall S s (.58W, + 50) not exceed 25% of rated thermal power.
The definitions used above for the APRM scram trip apply.
In the event of operation with a maximum fraction limiting power density (MFLPD) greater than the fraction of rated l
power (FRP), the setting shall be modified as follows:
S s (.58Wo + 50)
FRP MFLPD The definitions used above for the APRM scram trip apply.
l The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than 1.0, in which case the actual operating value will be used.
'This may also be performed by increasing the APRM gain by the inverse ratio, MFLPD/FRP, which accomplishes the same degree of protection as reducing the trip setting by FRP/MFLPD.
1.1/2.1-3 Amendment No. 147
l QUAD CITIES DPR-29 H.
Recirculation Pump Flow limitations H.
Recirculation Pump Flow limitations 1.
Whenever both recirculation pumps Recirculation pumps speed shall be are in operation, pump speeds shall checked daily for mismatch.
be maintained within 10% of each other when power level is greater i
1 than 80% and within 15% of each other when power level is less than 80%.
2.
If Specification 3.6.H.1 cannot be met, one recirculation pump shall be tripped.
3.
During Sinale Loop Operation for l
more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the following restrictions are required:
a.
The MCPR Safety Limit shall be increased by 0.01 (T.S.
l 1.lA);
I b.
The MCPR Operating Limit, as specified in the CORE OPERATING LIMITS REPORT, shall be increased by 0.01 (T.S. 3.5.K);
c.
The flow biased APRM Scram and Rod Block Setpoints shall be reduced by 3.5% to read as follows:
l T.S. 2.1.A.1; S s.58WD + 58.5 T.S. 2.1.A.1;*
S s (.58WD + 58.5) FRP/MFLPD T.S. 2.1.B; S s.58WD + 46.5 T.S. 2.1.B;*
S s (.58WD + 46.5) FRP/MFLPD i.S. 3.2.C (Table 3.2-3 ;,
APRM U) scale)s (.58WD + 46.5)
FRP/MF.PD
- In the event that MFLPD l
exceeds FRP.
l l
3.6/4.6-11 Amendment No. 147 l
QUA0 CITIES 1
DPR-29 d.
The flow biased RBM Rod Block setpoints, as specified in the CORE OPERATING LIMITS REPORT, shall be reduced by 4.0%.
e.
The recirculation pump in the idle loop shall be electrically prohibited from starting except to permit testing in preparation for returning to service.
4.
With no reactor coolant system recirculation loops in operation reduce core thermal powertolessthen25%of rated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and place the unit in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
Idle Recirculation Loop 5.
Idle Recirculation Loop Startup Startup The temperature differentials and An idle recirculation pump flow rates shall be determined to be shall not be started unless within the limits within 15 minutes i
the temperature differential prior to startup of an idle between the reactor vessel-recirculation loop.
steam space coolant and the bottom head drain line coolant is less than or equal to 145'F*, and:
a.
When both pumps have been idle,-unless the-temperature differential between the reactor coolant within the idle loop to be started up and the coolant in the reactor pressure vessel is less than or equal to 50*F, or b.
When only one loop has been idle, unless the l
temperature differential between the reactor coolant within the idle and operating l
recirculationloopsis less than or equa to 50'F and the speed of the operating pumps is less than or equal to 45% of rated pump speed.
00nly applicable with reactor pressure vessel steam space pressure it 25 psig.
I 3.6/4.6-12 Amendment No. 147 l
a QUAD CITIES 1
-l DPR-29 1.
Shock Suppressors (Snubbers)
I.
Shock Suppressors (Snubbers)
The following surveillance requirements apply to all snubbers on safety-related piping systems.
1.
Visual inspections shall be 1.
During all modes of performed in accordance with operation except the following schedule Shutdown and Refuel, all utilizing the acceptance snubbers on safety-criteria given by related piping systems Specification 4.6.I.2.
shall be operable except as noted in 3.6.I.2 following.
Number of Snubbers Found Inoperable During Next Required Inspection Inspection or During Interval l
Inspection Interval 0
18 months l
i25%
1 12 months z25%
2 6 months 125%
3,4 124 days 125%
5,6,7 62 davs f25%
18 31 days f25%
The required inspection interval shall not be lengthened more than one step at a time.
l 3.6/4.6-12a Amendment No. 147
QUAD CITIES DPR-29 H.
Recirculation Pump Flow limitations The LPCI loop selection logic is described in the SAR, Section 6.2.4.2.5.
For some limited low probability accidents with the recirculation loop operating with large speed differences, it is possible for the logic to select the wrong loop for injection.
For these limited conditions, the core spray itself is adequate to prevent fuel temperatures from exceeding allowable limits. However, to limit f
the probability even further, a procedural limitation has been placed on the allowable variation in speed between the recirculation pumps.
The licensee's analyses indicate that above 80% power the loop select logic could not be expected to function at a speed differential of 15%.
Below 80% power, the loop select logic would not be expected to function at a speed differential of 20%. This specification provides a margin of 5% in pump speed differential before a problem could arise.
If the reactor is operating on one pump, the loop select logic trips that pump before making the loop selection.
Analyses have been performed which support indefinite single loop operation provided the appropriate restrictions are implemented within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The MCPR Safety Limit has been increased by 0.01 to account for core flow and TIP reading uncertainties which are used in the statistical analysis of the safety limit. The MCPR Operating Limit, as specified in the CORE OPERATING LIMITS REPORT, has also been increased by 0.01 to maintain the same margin to the safety limit as during Dual loop operation.
The flow biased scram and rod block setpoints are reduced to account for uncertainties associated with backflow through the idle jet pumps when the operating recirculation pump is above 20-40% of rated speed. This assures that the flow biased trips and blocks occur at conservative neutron flux levels for a given core flow.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperature shall be within 50 'F of each other prior to startup of an idle loop. The loop temperature must also be within 50 'F of the reactor pressure vessel steam space coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles. Since the coolant in the bottom of the vessel is at a lower temperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the temperature difference were greater than 145 'F.
Additionally, asymmetric speed operation of recirculation pumps during idle loop startup induces levels of jet pump riser vibration that are higher than normal. The specific limitation of 45% of rated pump speed for the operating recirculation pump prior to the start of the idle recirculation pump ensures that the recirculation pump speed mismatch requirements presented in Specification 3.6.H.1 are maintained.
I.
Snubbers All snubbers are required OPERABLE te ensure that the structural integrity of the reactor cow t system and all other safety-related systems is maintained dur
, nc following a seismic or other event initiating dynamic loads MutGers excluded from this inspection 3.6/4.6-24 Amendment No. 147
QUA0 CITIES DPR-29 program are those installed on non-safety-related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.
Inspections performed before that interval has elapsed may 1
i be used as a new reference point to determine the next inspection.
However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
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l 3.6/4.6-24a Amendment No. 147 l
4 p* *EGuq p
UNITED STATES 3
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 206660001
%...../
i COMMONWEALTH EDISON COMPANY
- l AJQ IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 00AD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 143 i
License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 26, 1993, 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 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 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.
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:
. B.
Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.143, are hereby incorporated in the license. The licensee sha11' operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION dlQ.
Robert A. Capra, Director Project Directorate III-2 Division of ' Reactor Projects -
III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 16, 1994
i 4
4 ATTACHMENT TO LICENSE AMENOMENT NO. 143 i
FACILITY OPERATING LICENSE N0. DPR-3Q DOCKET N0. 50-265 i
Revise the Appendix A-Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
j REMOVE INSERT 1.1/2.1-2 1.1/2.1-2 3.6/4.6-5b 3.6/4.6-5b i
3.6/4.6-5b(i) 3.6/4.6-13a 3.6/4.6-13a 1
t 4
I i
4 a
OUAD CITIES DPR 30
~
Where:
D.
Reactor Water Lsvel (Shutdown Condition)
FRP =
fraction of rated thermal Whenever the reactor is in the shutdown power (2511 MWt)
I condition with irradiated fuelin the reactor.
vessel, the water level shall not be less MFLPD =
msximum fraction of than that corresponding to 12 irgches limiting power density above the top of the active fuel when it where the limiting is seated in the core, power density for each bundle is the design linear heat generation rate for Top of active fuelis defined to be 360 that bundle.
inches above vessel zero (See Bases
(
I 3.2!.
The ratio of FRP/MFLPD shall be set equal to 1.0 unless the actual operating value is less than 1.0 in which case the actual operating value will be used. This adjustment may also be performed by increasing the APRM gain by the inverse ratio,
(
MFLPD/FRP, which accomplishes the same degree of protection as reducing l
the trip setting by FRP/MFLPD, 2.
APRM Flux Scram Trip Setting (Refueling or Startup and Hot Standby Mode)
When the reactor mode switch is in the Refuel or Startup Hot Standby position, the APRM scram shall be set at less than or equal to 15% of rated neutron flux.
l 3.
IRM Flux Scram Trip Setting The IRM flux scram setting shall be set at less than or equal to 120/125 of full scale.
B.
APRM Rod Block Setting The APRM rod block setting shall be as shown in Figure 2.1-1 and shall be:
S s (0.58Wo + 50) 1.1/2.1-2 Amendment No.143 l
1 l
QUAD-CITIES l
- 3. During Single Loop Operation for more than l
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the following restrictions are
)
required:
j
- a. The MCPR Safety Limit shall be increased by 0.01 (T.S.1.1 A);
]
- b. The MCPR Operating Limit, as specified in the CORE OPERATING LIMITS REPORT, shall be increased by 0.01 i
(T.S. 3.5.K):
'j j
Block Setpoints shall be reduced by l
3.5% to read as follows:
' T.S. 2.1. A.1; S 1 58 WD + 58.5 1
T.S. 2.1.A.1 ;
- S 1(.58 WD + 58.5) FRP/MFLPD T.S 2.1.B:
I S 1 58 WD + 46.5 j
\\
T.S. 2.1.B, j
S 1(.58 WD + 46.5) FRP/MFLPD i
a T.S. 3,2.C (Table 2.1-3);'
APRM upscale 1(.58 WD + 46.5)
FRP/MFLPD In the event that MFLPD exceeds FRP.
1 i
- d. The flow biased RBM Rod Block
}
setpoints, as specified in the CORE
?
OPERATING LIMITS REPORT, shall be reduced by 4.0%.
- e. The recirculation pump in the idle loop shall be electrically prohibited from j
starting except to permit testing in preparation for returning to service.
i l
1 3.6/4.6-5b Amendment No. 143
1 QUAD CITIES DPR-30 4.
With no reactor coolant system recirculation loops in operation reduce core thermal powertolessthen25%of rated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and place the unit in hot shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
. Idle Recirculation Loop 5.
Idle Recirculation Loop Startup Startup The temperature differentials and An idle recirculation pump flow rates shall be determined to be shall not be started unless within the limits within 15 minutes the temperature differential prior to startup of an idle between the reactor vessel recirculation loop.
steam space coolant and the bottom head drain line coolant is less than or equal to 145'F*, and:
a.
When both pumps have been idle, unless the temperature differential between the reactor coolant within the idle loop to be started up and the coolant in the reactor pressure vessel is less than or equal to 50*F, or b.
When only one loop has been idle, unless the temperature differential between the reactor coolant within the idle and operating recirculation loops is less than or equal to 50*F and the speed of the operating pumps is less than or equal to 45% of rated pump speed.
00nly applicable with reactor pressure vessel steam space pressure 2 25 psig.
3.6/4.6-5b(i)
Amendment No. 143 l
QUAD-CITIES
~
DPR-30 H.
Recirculation Pump Flow limitations The LPCI loop selection logic is described in the SAR, Section 6.2.4.2.5.
For some limited low probability accidents with the recirculation loop operating with large speed differences, it is possible for the logic to select the wrong loop for injection. For these limited conditions, the core spray itself is adequate to prevent fuel temperatures from exceeding allowable limits. However, to limit the probability even further, a procedural limitation has been placed on the allowable variation in speed between the recirculation pumps.
The licensee's analysis indicated that above 80% power the loop select logic could not be expected to function at a speed differential of 15%. Below 80% power, the loop select logic would not be expected to function at a speed differential of 20%. This specification provides a margin of 5% in pump speed differential before a problem could arise. If the reactor is operating on one pump, the loop select logic trips that pump before making the loop selection.
Analyses have been performed which support indefinite single loop operation provided the appropriate restrictions are implemented within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The MCPR Safety Limit has been increased by 0.01 to account for core flow and TIP reading uncertainties which are used in the statistical analysis of the safety limit. The MCPR Operating Limit, as specified in the CORE OPERATING LIMITS REPORT, has also been increased by 0.01 to maintain the same margin to the safety limit as during Dual Loop operation.
The flow biased scram and rod block setpoints are reduced to account for uncertainties asscciated with backflow through the idle jet pumps when the operating recirculation purup is above 20-40% of rated speed. This assures that the flow biased trips and blocks occur at conservative neutron flux levels for a given core flow.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperature shall be within 50 0F of each other prior to startup of an idle loop. The loop temperature must also be within 50 oF rif the reactor pressure vessel steam space coolant temperature to prevent thermal shock to the recirculation pump and recirculation nozzles. Since the coolant in the bottom of the vesselis at a lower temperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the temperature difference were greater than 145 oF.
Additionally, asymmetric speed operation of recirculation pumps during idle loop startup induces levels of jet pump riser vibration that are higher than normal. The specific limitation of 45% of rated pump speed for the operating recirculation pump prior to the start of the idle recirculation pump ensures that the recirculation pump speed mismatch requirements presented in Specification 3.6.H.1 are maintained.
3.6/4.6-13a Amendment No.
143