ML20059E970
| ML20059E970 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/27/1990 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059E973 | List: |
| References | |
| NUDOCS 9009110044 | |
| Download: ML20059E970 (14) | |
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UNITED STATES e
e NUCLEAR REGULATORY COMMISSION
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l PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA PNER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC C0n'ANY 4
f DOCXET NO. 50-272' SALEr GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPTRATING LICENSE Amendment No.113
~ License No. DPR-70 4
1.
The Nuclear Regulatory Comission (the Comission 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 Electric Company thelicensees) dated February 22, 1990, and supplemented by letter dated May 29, 19F complies with the standards and requirements of the Atomic Ene of 1954 as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter 1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 conpliance with the Comission's regulations set forth in 10 CFR Chapter 1; D.
The issuance of this amendment will not be inimical' to the comon defense and security or to the health and cafety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable reo,uirements 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 2.0.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
9009110044 900827 PDR ADOCK 05000272 o
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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. 113, are hereby incorporated-in the license.
The licensee shal'1 operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date' oi' issuance to be implemented within 60 days of-the'date of issuance.
FOR THE NUCLEAR REGULATORY. COMMISSION
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k Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects'- 1/11
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Attachment:
Changes to the Technical Specifications l
Date of Issuance:.
August 27, 1990 k
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L (2) Technical Specifications and. Environmental Protection Plan >
1 ine Technical Specifications contained in. Appendices A and B'.
as revised through Amendment'No. 113.- are hereby. incorp' orated 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 to be' e
3 implemented within 60 days of the date of issuance FOR THE -NUCLEtR REGULATORY COMMISSION
/s/ J. Stone for We),ter.R. Butler, Director Project Directorate 1-2 Division of_ Reactor Projectsf..i/11
Attachment:
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Changes to the Technical
. Specifications Date of Issuance:
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ATTACHMENT.TO. LICENSE. AMENDMENT WO.113
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FACILITY'.0PERATING. LICENSE WO. DPR.70 DOCKET NO. 50 272 Revise Appendix A as-follows:
Remove.Pages Insert Pages:
3/4 1-5 3/4-1-5 3/4 1-Sa 3/4 1-Sa B 3/4 1-2 B 3/4 1-2 I
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REACTIVITY CONTROL SYSTEMS k
MODERATOR TEMPERATURE COEFFICIEN_I 1 LIMITING CONDITION TOR OPERATION-F 3.1.1.4 The moderator temperature coe'fficient (MTC) shad be:
a..
.Less positive than 0 delta k/k/*F for the all rods eithdravr.,
beginning of cycle life (BOL), hot zero THERMAL POWER condition, b.
Less negative than -4.4 x 10' delta k/k/*F'for the-all rods,
- l' withdrawn, end of cycle life (EOL).. RATED THERMAL POWER E,
condition.
APPL 1 cab 1LITY: Specification 3.1.1.4.a - MODES ~l' snd 2* onlyw 1
Specification 3.1.1.4.b MODES 1, 2 and 3 only#
ACTION:
With the MTC more positive than the. limit of 3.1.1.4.a,'above,'
a.
operations in MODES 1 and 2 may proceed-provided:
1.
Control rod withdrawal limits are established 'and maintaine6 =
sufficient to rostore the-MTC to less positive than 0 delta k/k/'r witMn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be 'in HOT STANDBY within the i
next 6' hours. These withdrawal limits shall-be in addition to the insertion limits of Specification 3.1,3.6.
2, The control-rods are maintained within th'e withdrawal-linits established above until a. subsequent calculation verifies thst the MTC has been restored to within its limit for tha all rods withdrawn condit.
3.
A Special' Report is prepared a-d submitted-to-the Commission pursuant to Specif! ation 6.9.! within 10 days, ' describing the valu of the m.
,und MTC, the intera control rod fithdrawal limits and the predicted. average core:burnup
..seessary for restoring the'-positive MTC to within its limit for the all rods withdrawn condition.
b.
With the MTC more negative than the limit' o'f 3;1.1.4 b,. above, be -
in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- With K,gg greater than or equal to.'i.0-
- See Special Test Exception 3.10.3 l
SALEM - UNIT 1 3/4 1-5 Amendment No. 113
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REACTIVITY CONTROL SYSTEMS
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MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.4 The MTC shall be determined to be within its limits during each fuel cycle as follows:
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a.
The MTC shall be measured and compared to the BOL limit of __
Specification 3.1.1.4.a above, prior to initial operation above
,i 5% of RATED THERMAL POWER, af ter each fuel loading, j
b.
TheMTCshg11bemeasuredatanyTHERMALPOWERandcomparedto
-3.7 x 10' delta k/k/*F (all rods withdrawn, RATED THERMAL POWER-l condition) within 7 EFPD after reaching an equilibrium boron
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concentration of 300 ppm In the event theMTCismorenegativethan-3.7x10,ghiscomparisenindicates l
delta k/k/'F, the MTC-shall be rameasured, and compared to the-EOL MTC limitiof spei '#ication 3.1.1.4.b, at least ot.ee per 14 EPPD during the rei iraof the fuel cycle.
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t SALEM UNIT 1 3/4 1-Sa Amendment No. 113<
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-3/4.1' REACTIVITY CONTROL SYSTEM 3J N
BASES 3 /4.1.1. 4 MODERATOR TEMPERATURE COEFFICIENT (MTC) (Continued)
The MTC values of this specification are applicable to a specific set of, plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in
~
order to permit an accurate comparison.
The most negative MTC value' equivalent to the most positive: moderator density coefficient (MDC), was obtained-by incrementally correcting the MDC used in the FSAR analysis to nominal operating conditions.
These corrections involved: (1) a conversion of the MDC used in the FSAR analysis to its equivalent MTC, based on the rate of change of moderator density with temperature at RATED THERMAL POWER conditions, and (2) subtracting from this value the largest differences in MTC observed between EOL, all' rods-withdrawn,-
RATED THERMAL POWER conditions,'and those most adverse conditions of moderator temperature and pressure, rod insertion,-axial power skewing, and xenon j
concentration that can occur in normal operation and-lead to a significantly l
more negative EOL MTC at RATED THERMAL POWER. These corrections transformed
'l theMDCva{ueusedinthePSARanalysisintothelimit{ngMTCvalue'of 1;
4.4 x 10 delta k/k/'F. The MTC value of 3.7 x 10 delta k/k/*F-represents a conservativ3 value (with corrections for burnup and soluble boron) at a core con >it; n of 300 ppm equilibrium boron concentration and'is
- obtained bg making ti $se correctice.. to the limiting MTC value
- a. 4 x 10 delta k/k/'F.
The_ surveillance requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm.that the MTC remains with its limits since'this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY 1
This specification e;:ures that the reactor will not be made critical-with the Reactor Coolant System average temperature.less than-541*F. This limitation is required to ensure 1) the_ moderator: temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation'is within its normal operating range, 3) the P-12 interlock is above its setpoint, 4) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and 5) the reactor pressure vessel.is-above its minimum RT NDT temperature.
1
$ALEM' UNIT 1 B3 1-2 Amendment No. 113
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%,,...*f pUBLIC. SERVICE. ELECTRIC.& GAS. COMPANY PWILADELPWI A. ELECTRIC.CONPANY DELMARVA. POWER.AND. LIGHT. COMPANY l
- ATLANTIC. CITY. ELECTRIC.CONPANY DOCKET NO. 50-311 S ALEN. GENERAT I NG. STAT I ON.. UN I T. WQ. 2 AMENDMENT.TO. FACILITY.0PERATING LICENSE 1
Amendment No. 94 License
.o. DPR-75'
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The Nuclear Regulatory Comission (the ComN =on or the NRC) h'as 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 Electric Company thelicensees)' dated February 22,'1990,. and supplemented by. letter-dated May 29~, 1990,.
complies with the standards and requirements 'of the Atomic; Energy Act of 1954, as amended (the Act), and the Comission's rules and' regulations set forth in 10 CFR Chapter-1; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 1
C.
There is reasonable assurance: (1).thattheactivitiesauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will'be conducted-int compliance with the Comission's regulations set-forth in 10 CFR-Chapter I; 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.
I 2
%cordingly, the license is amended by changes to the Technical Specifica-tiov as indicated in the attachment to this license ameidnent, and paiagraph 2.C.(2) of Facility Operating License No. DPR45 is hereby
.: rended to read as fellows:
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2 (2) Technical Specifications and Environmental Protection Plan J
The Technical Specifications contained in' Appendices A and B, as.
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revised thr^ ugh Amendment No. 94, 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 issuanct to be implemented within 60 days of the date of issuance.
FOR THE~ NUCLEAR REGULATORY. COMMISSION-
$/
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&, Walter R. Butler, Director Ffr Project Directorate 1..
Division of, Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of issuance: August 27, 1990 4
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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. 94, are hereby incorporated in> the license. The licensee shall coerate the facility in accordance with the Technical Specifications. '
3.
This license _ amendment is effective as of its date of issuance to be-implemented within 60 days of the datc cf issuance.
FOR.THE NUCLEAR' REGULATORY COMMISSION'
/s/ J. Stone for Walter R. Butler, Director Project Directorate I-2 Division of Rehetor Projects - 1/11'
Attachment:
Changes to the Technical Specifications Date of Issuance:- August 27, 1990 1
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-ATTACHMENT.T0 LICENSE. AMENDMENT.N0;.94..
FACILITY OPERATING. LICENSE NO..DPR DOCKET NO. 50-311-Revise Appendix A as follows:
Remove.Pages
. insert Pages 3/4. 1-4 3/4 1-4 3/4 1-5
- 3/4 '1-5 B 3/4 1-2 B 3/4 1-2 e
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REACTIVITY CONTROL SYSTEMS' MODERATOR TEMPERATURE COEFFICIENT w
LIMITING CONDITION FOR OPERATION.
l 3.1.1.3 The moderator temperature coefficient (MTC) shall be; a.
less positive than 0 delta k/k/'F for the all rods. withdrawn, beginning of cycle life (BOL), hot zero THERMAL POWER condition..
b.- -less negative 1.than -4.4 x.10-4 delta k/k/*F for the all rods-l' withdrawn end of cycle life (EOL), RATED THERMAL POWER condition. :
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-1 APPLICABILITY: Specification'3.1.1.3.a"- MODES 1 and 2* only#
Specification 3.1.1.3 b - MODE.3 1, 2 and 3 only#
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ACTION i
a.
.With the Mrc more positive than the limit of 3.1.1.3.a. ab'ove.,
j operations in MODES: 1 and.2 may proceed provided:
1.
Control rod withdrawal 1'imits are established and. maintained sufficient to restore the MTC to less positive than-O delta k/k/'F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be'in HOT-STANDBY within the j
next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These withdrawal limits shall be.in addition to Q
the insertion limits of Specification 3.1.3.6.
I 2.
The control rods are maintained within thc~ withdrawal limits l
established above until a subsequent calculation verifies that the MTC has been restored to within its limit-for the all rods withdrawn condition.
.[
i 3.
In lieu of any other report required by ' Specification '6.9.1,' a Special Report is prepared and submitted to the' Commission.
- pursuant to Specification-6.9.2 within'10; days, describing the j
value of the measured MTC, the interia control-rod withdrawal j
limits and the predicted average core burnup necessary for restoring the positive MTC to 'within its limit for the all-rodre l
withdrawn condition.
L b.
With the MTC more negative than the limit of 3.1.li3.b, above, be in.
i HOT SEUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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- With Keff ;reater than-or equal to 1.0 t
- See Special Test Exception 3.10.3 l
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SALEM - UNIT 2 3/4 1-4 Amendment No. 94 f
1 i
i REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to b:. within its limits during each fuel
~
~
cycle as follows:'
a.
The MTC shall be measured-and compared to the BOL limit of-Specification 3.1.1.3.a. abovo, prior to initial operation above 54-of-RATED THERMAL POWER, ~after ' each fuel loading.
i b.
The MTC 'st;gil b'e measured at any THERMAL POWER and comparod to.
-5.7 x 10' delta k/k/*F (all rods withdrawn, RA'dd THERMAL POWER' condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm. In-the evept this comparison indicates the i
MTC is more negative.than -3.7 x 10 delta k/k/*F, the MTC shall be ]'I
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remeasured,'and compared to the EOL MTC limit of specification 3.1.1.3.b at least once;per l'4 EFPD during the remainder of the fuel cycle.
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i SALEM -' UNIT 2 3/4 1-5 Amendment No.
94
s 3/4.1' REACTIVITY CONTROL SYSTEMS
.BASESL 3 /4.1.1. 3 MODERATOR TEMPERATURE COEFFICIENT (MTC) '(Continued)
The MTC values of this specification are applicable to a specific sr.t of plant conditions; accord'ngly, verification of MTC values at conditions other than'those explicitly stated will require extrapolation ~to those conditions in ordor to permit an accurate conparison.
The most negative MTC value equivalent to the most positive moderator density coefficient (HDC), was.obtained'by incrementally correcting the MDC used in the FSAR' analysis' to'*.ominal operating conditions. These corrections involved: (1) a conversion of *.he MDC used in the FSAR analysis to its equivalent MTC, based on the rate of change of moderator density with temperature at RATED THERMAL POWER. conditions, and (2) subtracting-from this value' the largest differences in MTC observed between EOL, all. rods withdrawn, RATED THERMAL POWER conditions, and those most adverse conditions of moderator temperature and pressure, rod ~ insertion, axial power skewing. and xenon concentration that can occur in normal operation and lead to a significantly more negative E0L MTC at RATED THERMAL POWER.
These corrections transformed the KDC vajue _used in the FSAR analysis into the limit {ng MTC value of 4.4 x 10
. delta k/k/'F.
The MTC value'of -3.7 x 10 delta k/k/*F represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and is obtained bg mating thesel corrections to the limiting MTC value 3
4.4 x 10 delta k/k/'F.
}
The surveillance requirements for measurement of_the.HTC'at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains with its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.
3 /4.1.1. 4 MINIMUM TEMPERATURE'FOR CRITICALITY I
This specification ensures that the reactor will not be made critical l
with the Reactor Coolant System average. temperature less'=than $41*F..This limitation is required to ensure 1) the moderator temperature coefficientHis within it analyzed temperature range, 2) the-protective = instrumentation is within its normal operating range, 3) the P-12 interlock is above its setpoint, 4) the pressurizer -is capable of beingJin an OPERABLE status with a steam bubble, and 5) the reactor pressure vessel-is 'above its minimum RT NDT temperature.
1 SALEM - UNIT 2 B 3/4 1 2 Amendment No.
94
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