ML20070K990
| ML20070K990 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/20/1994 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K992 | List: |
| References | |
| NUDOCS 9407280137 | |
| Download: ML20070K990 (15) | |
Text
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UNITED STATES i
S NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2055M001
,5 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NVCLEAR GENERATING STATION. VNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 133 License No. DPR-75 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Elictric Company (the licensees) dated June 11, 1993 and supplemented by letters dated July 19, August 3, and September 16, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Corraission'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: (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 set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense anti 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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-75 is hereby amended to read as follows:
9407280137 940720 DR ADOCK 050003}1
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, (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No.133, 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 its date of issuance and shall be implemented prior to restart from the eighth refueling outage, currently scheduled to end on December 13, 1994.
FOR THE NUCLEAR REGULATORY COMMISSION 0m
.l$
Charles L. Miller, Director Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
i Changes to the Technical l
Specifications Date of Issuance: July 20, 1994
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.. ~. - - - - - -... -. - -.. -
ATTACHMENT TO LICENSE AMENOMENT NO.111 FACILITY OPERATING LICENSE NO. OPR-75 DOCKET NO. 50-311 Revise Appendix A as follows:
Remove Paaes Insert Pagn 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-7 3/4 1-7 3/4 1-8 3/4 1-8 3/4 1-11 3/4 1-11 3/4 1-12 3/4 1-12 3/4 1-12a 3/4 9-1 3/4 9-1 3/4 10-1 3/4 10-1 B 3/4 1-3 B 3/4 1-3 B 3/4 1-4 8 3/4 1-4 B 3/4 1-5
)/4.1 REACTIVITY COtfrROL SYSTEMS
,]/4J 1 BORATION CONTROL S W OWN MARGIN - T
> 200*F avg
,1 AMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.6% delta k/k. l APPLICABILITY: MODES 1, 2*,
3, and 4.
ACTION:
With the SHUTDOWN MARGIN less than 1.6% delta k/k, immediately initiate and continue boration at 2 33 gpm of a solution containing 2 6,560 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.
SURVE1LLANCE REQUIREMENTS i
1 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal co 1.6% delta k/k:
l a.
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> af ter detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereaf ter while the rod (e) is inoperable.
If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod (s),
b.
When in MODE 1 or MODE 2 with K greater than or equal to 1.0, at leastonceper12hoursbyveriIhkngthatcontrolbankwithdrawalis within the limits of Specification 3.1.3.5.
c.
When in MODE 2 with K less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achievingreactorcriIkbalitybyverifyingthatthepredicted critical control rod position is within the limits of i
Specification 3.1.3.5.
- See Special Test Exception 3.10.1 SALEM - UNIT 2 3/4 1-1 Amendment No.133
1 REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T
$ 200*F avg LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than'or equal to 1.0% delta k/k.
APPLICABILITY: MODE 5.
ACTION:
With the SHUTDOWN MARGIN less than 1.0% delta k/k, immediately initiate and continue boration at 2 33 gpm of a solution containing 2 6,560 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REQUIREMElfrS r
4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.0% delta k/k:
a.
Within i hour after detection of an inoperable control rod (s).and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereaf ter while the rod (s) is inoperable. If the inoperable control rod is immovable or untrippable, the SHITrDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable control rod (s),
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following i
factors:
1.
Reactor coolant system boron concentration, 2.
Control rod position, 1
3.
Reactor coolant system average terrperature, 4.
Fuel burnup based on gross thermal energy generation, 5.
Xenon concentration, and 6.
Samarium concentration.
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l SALEM UNIT 2 3/4 1-3 Amendment NO. 133 l
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i REACTIVITY CONTROL SYSTEMS 3/4.1.2 BORATION SYSTEMS FLOW PATHS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE:
A flow path from the boric acid tanks via a boric acid transfer pump a.
and charging pump to the Reactor Coolant System if the boric acid I
storage tank in Specification 3.1.2.5a is OPERABLE, or b.
The flow path from the refueling water storage tank via a charging pump to the Reacter Coolant System if the refueling water storage tank in Specification 3.1.2.5b is OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one injection path is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:
a.
When the boric acid tank is a required water source, by verifying at least once per 7 days that:
(1)
The flow path from the boric acid tank to the boric acid transfer pump, the boric acid transfer pump, and the recirculation path from the boric acid transfer pump to the boric acid tank is 2 63'F, and (2)
The flow path between the boric acid transfer pump recirculation line to the charging pump suction line is k 50*F, b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked sealed, or otherwise secured in position, is in its correct position.
J SALEM UNIT 2 3/4 1-7 Amendment No. 133 w
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REACTIVITY CONTROL SYSTEMS FLOW PA'IHS - OPERATING
. LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boren. injection flow paths shall be OPERABLE:
a.
The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System.
b.
Two flow paths from the refueling water storage tank via charging pumps to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2,
3 and 4.
ACTION:
With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two boron injection flow paths to the Reactor Coolant System to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHOTDOWN MARGIN equivalent to at least 1%
delta k/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SNUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.2 Each of the above required flow paths shall be demonstrated OPERABLE:
a.
By verifying at least once per 7 days that:
(1)
The flow path from the boric acid tank to the boric acid transfer pump and from the recirculation line back to the boric acid tank is 2 63*F, and j
(2)
The flow path between the boric acid tank recirculation line to the charging pump suction line is 2 50*F, b.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
c.
At least once per 18 months during shutdown by verifying that each j
automatic valve in the flow path actuates to its correct position on j
a safety injection test signal.
d.
At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2.a delivers at least 33 gpm to the Reactor Coolant System.
j SALEM - UNIT 2 3/4 1-8 Amendment No. 133 i
REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - SWJrDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE :
a.
A boric acid storage system with:
1.
A minimum contained volume of 2,600 gallons, 2.
Between 6,560 and 6,990 ppm of boron, and 3.
A minimum solution temperature of 63*F.
l b.
The refueling water storage tank with:
1.
A minimum contained volume of 37,000 gallons, 2.
A minimum boron concentration of 2,300 ppm, and 3.
A minimum solution temperature of 35'F.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no borated water source OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one borated water source is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated j
OPERABLE:
a.
For the boric acid storage system, when it is the source of borated water at least once per 7 days by:
1.
Verifying the boron concentration of the water, 2.
Verifying the water level of the tank, and i
3.
Verifying the boric acid storage tank solution temperature when it is the source of borated water, b.
For the refueling water storage tank by:
1 1.
Verifying the boron concentration at least once per 7 days, 2.
Verifying the borated water volume at least once per 7 days, and 3.
Verifying the solution temperature at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, when it is the source of borated water and the outside air temperature is less than 35'F.
SALEM - UNIT 2 3/4 1-11 Amendment No. 133
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REACTIVITY CONTROL SYSTEMS BOPATED WATER. SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water. source (s) shall be OPERABLE as required by Specification 3.1.2.2:
a.
A boric acid storage system with:
1.
A contained volume of borated water in accordance with figure 3.1-2, 2.
A Boron concentration in accordance with Figure 3.1 2, and 3.
A minimum solution temperature of 63*F.
b.
The refueling water storage tank with:
1.
A contained volume of between 364,500 and 400,000 gallons of water, 2.
A boron concentration of between 2,300 and 2,500 ppm, and 3.
A minimum solution temperature of 35'F.
APPLICABILITY: MODES 1, 2,
3 and 4.
ACTION:
a.
With the boric acid storage system inoperable and being used as one of the above required borated water sources, restore the storage system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least it delta k/k at 200'F; restore the boric acid storage system to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With the refueling water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPRRABLE:
a.
For the boric acid storage system, when it is the source of borated water at least once per 7 days by:
1.
Verifying the boron concentration in each water source.
2.
Verifying the water level of each water source, and 3.
Verifying the boric acid storage system solution temperature, b.
For the refueling water storage tank by:
1.
Verifying the boron concentration at least once per 7 days, 2.
Verifying the borated water volume at least once per 7 days, and 3.
Verifying the solution temperature at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the outside air temperature is less than 35*F.
SALEM - UNIT 2 3/4 1-12 Amendment No. 133
BORIC ACID TANK CONTENTS BASED ON RWST CONCENTRATION m
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- 6,600 2 pNACQEPTA,BLE OPERAT)ON SS90 ppm (maximum)'M) l l
6,600 6,700 6,800 6,900 7,000 CONCENTRATION IN BAT ppm BORON SALEM. UNIT 2 3/4 1-12(a)
Amendment No. 133
3/4.9 REFUELING OPEPATIONS 3/4.9.1 BORON CONCENTPATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head closure bolts less than fully tensioned or witn ene head removed, the boron concentration of all filled portions of the
~
Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met:
Either a K,gg of 0.95 or less, which includes a 1% Ak/k a.
conservative allowance for uncertainties, or b.
A boron concentration of greater than or equal to 2000 ppm, which includes a 50 ppm conservative allowance for uncertainties.
APPLICABILITY: MODE 6*
ACTION:
With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at 2 33 gpm of a solution containing 2 6,560 ppm boron or its equivalent until K is reduced to less thanorequalto0.95ortheboronconcentrationisreskoredtogreaterthan g
or equal to 2000 ppm, whichever is the more restrictive. The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:
a.
Removing or unbolting the reactor vessel head, and b.
Withdrawal of any full length control rod in excess of 3 feet from its fully inserted position.
4.9.1.2 The boron concentration of the reactor coolant system and the refueling canal shall be determined by chemieml analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The reactor shall be maintained in MODE 6 whenever. fuel is in the reactor with the reactor vessel head closure bolts less than fully tensioned or with the head removed.
SALEM - UNIT 2 3/4 9-1 Amendment NO.
133
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t 3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN _ MARGIN LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of control rod worth and shutdown margin provided the reactivity equivalent to at least the highest estimated control rod worth is available for trip insertion from OPERABLE control. rod (s).
APPLICABILITY: MODE 2.
ACTION:
a.
With any full length control rod not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at 2 33 gpm of a solution containing 2 6,560 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
i b.
With all full length control rods inserted and the reactor suberitical by less than the above reactivity equivalent, immediately initiate and continue boration at 2 33 gpm of a solution containing 2* 6,560 ppm boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.
SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length rod either partially or FULLY WITHDRAWN shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
4.10.1.2 Each full length rod not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.
SALEM UNIT 2 3/4 10-1 Amendment No.133
REACTIVITY CONTROL SYSTEMS BASES 3/4.1.2 BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation.
The components required to perform this function include:
- 1) borated water sources, 2) charging pumps,
- 3) separate flow paths, 4) boric acid transfer pumps, and 5) an emergency power supply from OPERABLR diesel generators.
With the RCS average temperature above 200*F, a minimum of two boron injection flow paths are required to ensure single functional capability in the event an assumed failure renders one of the flow paths inoperable. The boration capability of either flow path is sufficient to provide a SHUTDOWN MARGIN from expected operating conditions of 1.6% delta k/k after xenon decay and cooldown to 200*F.
The maximum expected boration capability (minimum boration volume) requirement is established to conservatively bound expected operating conditions throughout core operating life. The analysis assumes that the most reactive control rod is not inserted into the core. The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires borated water from a boric acid tank in accordance with TS Figure 3.1 2, and additional makeup from eithert (1) the second boric acid tank and/or batching, or (2) a maximum of 41,800 gallons of 2,300 ppm borated water from the refueling water storage tank.
With the refueling water storage tank as the only borated water source, a maximum of 73,800 gallons of 2,300 ppm borated water is required. However, to be consistent with the ECCS requirements, the RWST is required to have a minimum contained volume of 350,000 gallons during operations in MODES 1, 2,
3 and 4.
The boric acid tanks, pumps, valves, and piping contain a boric acid solution concentration of between 3.75% and 4% by weight. To ensure that the boric acid remains in solution, the tank fluid temperature and the process pipe wall temperatures are monitored to ensure a temperature of 63*F, or above is maintained.
The tank fluid and pipe wall temperatures are monitored in the main control room. A 5'F margin is provided to ensure the boron will not precipitate out.
Should ambient temperature decrease below 63*F, the boric acid tank heaters, in conjunction with boric acid pump recirculation, are capable of maintaining the boric acid in the tank and in the pump at or about 63*F.
A small amount of boric acid in the flowpath between the boric acid recirculation line and the suction line to the charging purp will precipitate out, but it will not cause flow blockage even with temperatures below 50*F.
With the RCS temperature below 200*F, one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE OPERATIONS and positive reactivity change in the event the single injection system becomes inoperable.
SALEM - UNIT 2 B 3/4 13 Amendment No. 133
REACTIVITY CONTROL SYSTEMS BASES The boron capability required below 200*F is sufficient to preside a SHtt W WN MARGIN of 1% delta k/k after xenon decay and cooldown from 20C*F to 140*F.
This condition requires either 2,600 gallons of 6,560 ppm borated l
water fz7m the boric acid storage tanks or 7,100 gallons of 2,300 ppm borated l
water froe the refueling water storage tank.
The 37,000 gallons limit in the refueling water storage tank for Modes 5 and 6 io based upon 21,210 gallons that is undetectable due to lower tap location, 8,550 gallons for instrument error, 7,100 gallons required for shutdown margin, and an additional 140 gallons due to rounding up.
The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained water volume limits includs allor6nce for water not available because of discharge line location and other physical characteristics.
The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.
3/4.1.3. TVABLE CO!UROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3; limit the potential effects of rod mis-alignment on.
associated accident anBlyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits. OPERABLE condition for the analog rod position indicators is defined as being capable of indicating rod position to within 12 steps of the bank demand position for a range of positions. For the Shutdown Banks, and Control Bank A this range is defined as the group demand counter indicated position between 0 and j
30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn j
inclusive. This permits the operator to verify that the control rods in ;nere banks are either fully withdrawn or fully inserted, the normal operating modes j
for these banks.
Knowledge of these banks positions in these ranges satisfies j
all accident analysis assumptions concerning their rosition. The range for j
control Bank B is defined as the group demand counter it4icated position i
between 0 and 30 steps withdrawn inclusive, and between 160 and 214 cceps withdrawn inclusive. For Control Banks C and D the range is defined as the group demand counter indicated position between 0 and 228 steps withdrawn.
1 Comparison of the group demand counters to the bank insertion limits with verification of rod position with the analog rod position indicators (after
?Sermal soak af ter rod motion) is sufficient verification that the control rods are above the insertion limits. The full out position will be specifically established for each cycle by the Reload Safety Analysis for that cycle. This position will be within the band established by " FULL WITHDRAWN" and will te adminiceratively controlled. This band is allowable to minimize RCCA wear, pursuant to Information Notice 87-19.
SALEM - UNIT 2 B 3/4 1-4 Amendment NO. 133
i i
REACTIVITY CONTROL SYSTEMS l
BASES The ACTION statements which permit limited variation from the basic requirements are accompanied by additional restrictions which ensure that the original criteria are met, Mis-alignment of a rod-requires measurement of peaking factors or a restriction in THERMAL POWER; either of these restrictions provide assurance of fuel rod integrity during continued l
operation.
The reactivity worth of a mis aligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumption used in the accident analysis.
The maximum rod drop time restriction is consistent with the assumed rod drop time used in the accident analyses. Measurement with T
>541*F and with all i
reactor coolant pumps operating ensures that the measu$e8 drop times will be representative of insertion times experienced during a reactor trip at operating conditions.
Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verificat.sne required if t,1 automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LCO's are satisfied.
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SALEM - UNIT 2 B 3/4 1-5 Amendment No. 133
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