ML20236D959

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Amends 140 & 142 to Licenses DPR-44 & DPR-56,respectively, Revising Min Rate Required on Source Range Monitors for Withdrawal of Control Rods for Startup
ML20236D959
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 03/15/1989
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20236D962 List:
References
NUDOCS 8903230386
Download: ML20236D959 (14)
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Text

{{#Wiki_filter:____-_ - f[ j UNITED STATES g y' g NUCLEAR REGULATORY COMMISSION 7, j WASHINGTON, D. C 20555 PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COM i DOCKET NO. 50-277, PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. ? AMEN 0 MENT TO FACILITY OPERATING LICENSE Arendment No. 140 License No. DPR-44 1. The Nuclear Regulatory Comm% ion (the Comission) has found that: A. The application for amendn.ent by Philadelphia Electric Company, et al. (the licensee) dated October 21, 1988 as supplemented on November 30, 1988, 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 cf 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 iniinical to the comon defense and security or to the health or safety of the public; and E. The issuance of this amendment is in accordance with 10 CFP Part 51 of the Comission'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 2.C(2) of Facility Operating License No. OPR-44 is hereby amended to read as follows: 8 032sose6 890315 AD0CKjO500 7

l ? . (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 140, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of its date of issuance. FOR THE NUCLEAR REGULATORY COMMISSION v V Walter R. Butler, Director Project Directorate I-2 ' Division of Reacter Projects I/II {

Attachment:

Changes to the Technical Specifications Date of Issuance: March 15, 1989 1 1 i

~ 5 ATTACHMENT TO LICENSE AMENDMENT NO. 140 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Specifications with j the enclosed pages. The revised areas are indicated by marginal lines. Remove Insert iv iv 103 103 103a l 110 110 i 'i l

UNIT 2 i + PBAPS LIST OF FIGURES Figure Title Pg 1.1-1 APRM Flow Bias Scram Relationship To Normal Operating 16 Conditions 4.1.1 Instrument Test Interval Determination Curves 55 4.2.2 Probability of System Unavailability vs. Test Interval 98 3.3.1 SRM Count Rate vs. Signal-to-Noise Ratio '103a 3.4.1 DELETED 122 1 3.4.2 DELETED 123 1 3.5.K.1-1 MCPR Operating Limit vs. I, BP/P8X8R Fuel, Standard 142 Operating Conditions 3.5.K.1-2 MCPR Operating Limit vs. t, GE8X8EB Fuel, Standard 142a-1 Operating Conditions 3.5.K.1-3 MCPR Operating Limit vs. t, LTA310 Fuel, Standard 142a-2 Operating Conditions 3.5.K.2-1 MCPR Operating Limit vs. t, BP/P8X8R Fuel, Increased 142a-3 Core Flow 3.5.K.2-2 MCPR Operating Limit vs. I, GE8X8EB Fuel, Increased 142a-4 l Core Flow I 3.5.K 2-3 MCPR Operating Limit vs. t, LTA310 Fuel, Increased 142a-5 Core Flow

3. 5. K. 3 DELETED 142b 3,5.1.E Kf Factor vs. Core Flow 142d 3.5.1.F DELETED 142e 3.5.1.G DELETED 142f 3.5.1.H MAPLHGR vs. Planar Average Exposure, Unit 2, 142g P 8X8R Fuel, Type P80RB285, 100 mil channels l

l i l-Amendment No. JS, pp, 95, SS, 79, SJ, 108. IZ2,123,140 _jv-p

s UNIT 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.8 Control Rods (Cont'd.) 4.3.8 Control Rods (Cont'd.) 4. Control rods shall not be with-4. Prior to control rod drawn for startup or refueling withdrawal for startup unles; at least two source or during refueling range channels have an observed verify that at least count rate equal to or greater two source range l l than three counts per second.* channels have an observed count rate of at least three counts p'er second.* l S. During operation with limiting 5. When a limiting control control rod patterns as deter-rod pattern exists, an mined by'the designated quali-instrument functional test fied personnel, either: of the RBM shall be performed prior to with-drawal of the designated -rod (s). l a. Both RBM channels shall be operable, or b. Control rod withdrawal shall

  • May be reduced for startup be blocked, or only, provided at least c.

The operating power level three source range shall be limited so that channels have an observed the MCPR will remain above count rate and a signal- .the fuel cladding integrity to-noise ratio on or safety limit assuming a above the curve shown single error that results on Figure 3.3.1. in complete withdrawal of a single operable control rod. C. Scram Insertion Times C. Scram Insertion Times 1. The average scram insertion time, 1. After each refueling outage, based on the deenergization of and prior to synchronizing the scram pilot valve solenoids the me.in turbine generator as time zero, of all operable initially following restart control rods in the reactor of the plant, all operable power operation condition fully withdrawn insequence shall be no greater than: rods shall be scram time tested during operational % Inserted from Avg. Scram Inser-hydrostatic testing or Fully Withdrawn tion Times (sec) during startup from the fully withdrawn posi-5 0.375 tion with the nuclear 20 0.90 system pressure above 50 2.0 800 psig. 90 3.5 Amendment No. D, 98, 86, 140 -103-

Figure 3.3.1 PBAPS UNIT 2 SRM Count Rate Versus Signal-to-Noise Ratio ) 3.0 2.9 2.8 l 2.7 l 2.6 l 2.5 2.4 j 2.3 l 2.2 7 2.1 i 4 c.3 2.0 { l.9 1.8 i a \\ l e 1.7 a \\ z 1.6 l N 1.5 i \\ 1.4 \\ l I t.3 l \\ I 1.2 \\ l 1.1 \\ l' 1.0 x Nm 0.9 ~- 1 0.8 ~- 0.7 2 6 10 14 18 22 26 30 i Signal-to-Noise Ratio -103a-Amendment No.140

UNIT 2 4 P8APS 3.3.8 and 4.3.B BASES (Cont'd.) The requirement of at least 3 counts per second (may be reduced for start-up provided the count rate and signal-to-noise ratio is on or above the curve shown on Figure 3.3.1) assures that any transient, should it occur begins at or above the initial value of 10 8 of rated power used in analyses of transient cold conditions. One operable SRM channel would be adequate to monitor the d approach to criticality using homogeneous patterns of scattered control rod I withdrawal. A minimum of two operable SRM's are provided as an added j conservatism. j i 5. The Rod Block Monitor (RBM) is designed to automatically preven't*' fuel l damage in the event of erroneous rod withdrawal from locations of high power i density during high power level operation. Two channels are provided, and one of these may be bypassed from the console for maintenance and/or testing. Tripping l of one of the channels will block erroneous rod withdrawal soon enough to prevent i fuel damage. This system backs up the operator who withdraws control rods according to written sequences. The specified restrictions with one channel out of service conservatively assure that fuel damage will not occur due to rod withdrawal errors when this condition exists. ) A limiting control rod pattern is a pattern which results in the core being on a thermal hydraulic' limit (i.e., operating on a limiting value for APLHGR, LHGR, or MCPR as defined in Technical Specifications 3.5.I., 3.5.J and 3.5.K). During use of such patterns, it is judged that testing of the RBM system prior 1 to withdrawal of such rods to assure its operability will assure that improper l withdrawal does not occur. It is the responsibility of the Reactor Engineer to ] identify these liiniting patterns and the designated rods either when the patterns j are initially established or as they develop due to the occurrence of inoperable j control rods in other than limiting patterns. Other personnel qualified to q perform this function may be designated by the station superintendent. 4 l l l Amendment No. 23, 26, 140 -110-

y-i. 1 aactau T o ' UNITED STATES g _ [ .g NUCLEAR REGULATORY COMMISSION s 5 j WASHINGTON, D. C. 20656 %,.....,o! i s y j .g \\ PHILADELPHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AMD GAS CJMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO.'50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.142 License No. DPR-56 1. The Nuclear Regulatory Commission (the Comission) has found that: ] A. The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated October 21, 1988 at supplemented on November 30, 1988, complies with the standaros ond requirements of-theAtomicEnergyActof1954,asamended(theAct),andthe Comission'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 l authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wili 3e conducted in compliance with the Commission's regulations;- D. The issuance of this amendment will not be inimical. to the comon defense and security or to the health or safety 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 requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating Licensa No. DPR-56 is hereby amended to read as follows: ___m_______._.____.________m __m

1 1

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s 3 3 s. ~ t 1 j .(2) Technical Specifications The Technical Specifications contained in Appendices, A an'd B, as l revised through Amendment No. 142, are hereby. incorporated in the-I licease. PEC0 shall operate the facility in accordance with tha Technical Specifications. N-3, This-license amendment is effective as. of its date of issuance. i { FOR THE NUCLEAR REGULATORYs COMMISSION ,/ Walter R. Butler, Director l Project Directorate I-2 l Division of. Reactor Projects I/II i

Attachment:

s Changes to the Technical Specifications I ) Date of Issuance: March 15, 1989 s \\ \\ i t s k

3y-3- --- g m s ). I N '\\* ' '\\ i-s .s. q. .1 \\ l\\ \\ ( ' i, 3' ATTACliMENT TO LICENSE AMENDMENT NO.lgi s \\ ~' 3 \\ x \\ .\\ s \\ -\\ FACILITY OPERATING LICENSE NO. OPR-56 '\\ \\' s\\. s s \\ .x \\ DOCKET NO. 50-278 \\ . 1 t .'1 \\- i \\. \\ 3 s s c o' ' \\ Peplacesthe fo'llowing pa,ges of the Appendix A Technical Specifications with t \\ x the enclosed pages. The revisediareas are indicated by' marginal lines. s x 3 i Remove ~t .1, Inser_t_ 1-s iv iv Y 1, k 103 (

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m UNIT 3 'b .\\ PBAPS a LIST OF FIGURES Figure Title M-1.1-1 APRM Flow Bias Scram Relationship To" Normal Operating 16 Conditions 4.1.1, Instrument Test Interval Determination Curves 55 4.2.2 Probability of System Unavailability vs. Test Interval 98

3. 3.1 -

SRM Count Rate'vs. Signal-to-Noise Ratio 103a 3.4.1 DELETED 122 3.4.2 DELETED 123' s \\ 3.5.K.1 hlCPR Operating Limit vs. Tau, LTA. 142 3.5.K.2 HCPR.0perating Limit vs. Tau,'BP/P8X8R Fuel 142a 3.5.1.A DELETED 3.5.1.8 DELETED

3. 5. l. C OELETED 3.5.1.D DELETED 3.5.1.E Kf Factor vs. Core' Flow 142d 3.5.1.F DELETED 3.D.1.G DELETED 1
3. 5.1. H MAPLHGR vs. Planar Average Exposure, Unit 3 142g P8X8R Fuel (P80RB284H)

\\ 3.5.1.I MAPLHGR vs. Planar Average Exposbre, Unit 3 142h P8X8R and BP8X8R Fuel (P80RB299 and BP8DRB299)-

3. !!.1. J.

MAPLHGR vs. Planar Average Exposure, Unit 3 1421 BP8X8R Fuel (BP8DRB299H) 3.5.1.K MAPLHOR vs. Planar Average Exposure, Unit 3 '142j ix P8X8Q LTA (P80QB326) 3.6.1 Minimum Temperature for Pressure Tests such as 164 1< required by Section XI s 3,6. 2'. Minimum Temperature for Mechanical _Heatup or .164a Cooldown following Nuclear Shutdown 3.6.3 Minimum Temperature for Core Operation (Criticality) 1646 3.6.4 Transition Temperature Shift vs. Fluence 164c o 3;6.S Thenul Power Limits of Specifications 164d 3.6.F.3, 3.6.F.4, 3.6.F.5, 3.6.F.6 and 3.6'.F.7 s

3. '8.1 Site Boundary and Effluent Release Points 216n

.) 6.2-1 Management Organization Chart '244,, 1 6.2-2 Organization for Conduct of Plant Operation 245 , Amendment No. I#, (I, H, H, 62, M i 79, fi', IO#,107. IIf,126,1.42 ' f ,< q^ -1V" 'a 'o N y,5 > a h y x \\uO' e m 1 Q,& J". y-e + ~ e

UNIT 3 P8APS I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.8 Control Rods (Cont'd.) 4.3.B _ Control Rods (Cont'd.) 1 4. Control rods shall not be with-4. Prior to control rod drawn for startup or refueling withdrawal for startup unless at least two source or during refueling, l range channels have an observed verify that at least I count rate equal to or greater two source range l l than three counts per second.* channels have an observed count rate of at least l three counts per second.* 5. During operation with limitirq 5. When a limiting control control rod patterns, as deter-rod pattern exists, an mined by the designated quali-instrument functional test I fied personnel, either: c' ihe RBM shall be l performed prior to with-I drawal of the designated rod (s). l a. Both RBM channels shall be l operable, or i b. Control rod withdrawal shall

  • May be reduced for startup l

be blocked, or only, provided at least i c. The operatir.g power level three source range I shall be limited so that channels have an observed the MCPR will remain above . count rate and a signal-the fuel cladding integrity to noise ratio on or safety limit assuming a above the curve shown single error that results on Figure 3.3.1. in complete withdrawal of I a single operable control rod. l C. Scram Insertion Times C. Scram Insertion Times 1. The average scram insertion time, 1. After each refueling outage, based on the deenergization of and prior to synchronizing the scram pilot valve solenoids the main turbine generator l as time zero, of all operable initially following restart control rods in the reactor of the plant, all cperable power operation condition fully withdrawn insequence shall be no greater than: rods shall be scram time tested during operational % Inserted from Avg.. Scram Inser-hydrostaticstesting or Fully Withdrawn tionTimes(sec),_, during startup from the fully withdrawn posi-5 0.375 tion witn the nuclear 20 0.90 systelopressure above 50 240 830 psig. l 90 3.5 l 1 i -103-Amendmen t No. 74, (J, 79. L142 l, j, 4 c \\ '\\ L C 1 -

m Figurs 3.3.1 UNIT 3 SRM Count Race Versus Signal-to-Noise Ratio ') i i 3.0 l 2.9-2.8 a 2.7 i i 2.6 i f 2.5 1 2.4 - 2.3 i l I 2.2 k 7 2.I c. E' 2.0 i { l.9 t,a E l \\ n L.7- -\\ { S

c
1. 6 --

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== 1.5 \\ 1.4 \\ l L.3 i \\ l 1.2 s\\ l l t.1._ _.____ \\ l.0 - 0.9 - ------ J.s -- ~ \\ 0.7 t- ~ 2 6 to 14 18 22 26 30 l l Signal-to-Noise Ratio i -10?a. Amendment No. 142 l' .i 4 j tim -

UN!T 3 P8APS 3.3.8 and 4.3.B BASES (Cont'd.) The requirement of at least 3 counts per second (may be reduced for startup provided the count rate and signal-to-noise ratio is on or above the curve shown on Figure 3.3.1) assures that any transient, should it occur begins at or above the initial value of 10 8 of rated power used in analyses of transient cold conditions. One operable SRM channel would be adequate to monitor the approach to criticality using homogeneous patterns of scattered control rod withdrawal. A minimum of two operable SRM's are provided as an added conservatism. 5. The Rod Block Monitor (RBM) is designed to automatically prevent. damage in the event of erroneous rod withdrawal from locations of high. fuel power density during high power level operation. Two channels are provided, and one of these may be bypassed from the console for maintenance and/or testing. Tripping of one of the channels will block erroneous rod withdrawal soon enough to prevent fuel damage. This system backs up the operator who withdraws control rods i according to written sequences. The specified restrictions with one channel out of service conservatively assure that fuel damage will not occur due to rod withdrawal errors when this condition exists. A limiting control rod pattern is a pattern which results in the core being on a thermal hydraulic limit (i.e., operating on a limiting value for APLHGR, LHGR, or MCPR as defined in Technical Specifications 3.5.I., 3.5.J and 3.5.K). During use of such patterns, it is judged that testing of the RBM system prior to withdrawal of such rods to assure its operability will assure that improper withdrawal does not occur. It is the responsibility of the Reactor Engineer to identify these limiting patterns and the designated rods either when the patterns l are initially established or as they develop due to the occurrence of inoperable l l l control rods in other than limiting patterns. Other personnel qualified to l perform this function may be designated by the station superintendent. l 1 i 5 Amendment No. 33, 142 -110-}}

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