ML19332D485

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Amends 108 & 103 to Licenses DPR-19 & DPR-25,respectively, Correcting Discrepancy Between Tech Spec Table 3.2.2 Value for 4 Kv Emergency Bus Undervoltage Trip (3,092 Volts) & Current Trip Value (2,930 Volts)
ML19332D485
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 11/21/1989
From: Jocelyn Craig
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19332D486 List:
References
NUDOCS 8912040034
Download: ML19332D485 (12)
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l ?.; . 40 nsey'o:, 'A' UNITED STATES >8" ~% NUCLEAR REGULATORY COMMISSION l-W i l E' WASHINGTON, D. C. 20665 k... p o 'e 1 COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO PROVISIONAL OPERATINb LICENSE Amendment No. 108 j. License No. DPR-19 1.- The Nuclear Regulatory Comission (the Comission) hat found that: A. The application for amendment by the Comonwealth Edison Company - .(the licensee) dated March 28, 1988 complies with the stanciards and requirements of the Atomic Energy Act of 1954, as amenced '(the Act), and.the 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 (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 Comission's regulations; D. The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied, g20ggggQ$$ g7 P . ~

o 1. 2 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 Provisional Operating License No. DPR-19 is hereby amended to read as follows: B. -Technical Specifications ' The Technical Specifications contained in Appendix A, as revised through Amendment No. 108, are hereby incorporated in the license. The licensee shall operate the facility - in accordance with the Technical Specifications. L 3. -This license amendment is effective as of the date of its issuance. FOR E NUCLEAR REGULATORY COMMISSION h (-{} $p h \\n' John W. Craig, Director Project Directorate III-2' Division of Reactor Projects - III, IV, Y and Special Projects 4 Office of Nuclear Reactor Regulation t

Attachment:

Changes to the Technical l l Specifications I Date of Issuance: November 21, 1989 i y w sm-, - - ,--r-w .m-e w ~,

3 = g N.. .c ATTACHMENT TO LICENSE AMENDMENT NO. 108 PROVISIONAL OPERATING LICENSE DPR-19 DOCKET NO. 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.. REMOVE INSERT 3/4.2-10 3/4.2-10 B 2/4.2-33 B 3/4.2-33 B 3/4.2-33a i l. -.y-c y.- ,--.e.. _q, y..w, -.c 3 ---aw wt -aw-- * -w -r r 's-m'-- v = veT* e

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i: T t, 4 s DR(5Dth II -DPR 19 Amenment ho. 308 TABLt 3,2.2 IN51RUMENTAT10N THAL IN!11ATi$ 04 CONTROL 5 TH[ COR[ AND CONTAllM(N1 C00tlNG SYST[M5 - Min. ho, of Operable Inst. Channels per 1 rip Systeo (1) Trip function frir level Settino Remarks 2 Reactor Low 84" (plus 4, sinus 0 1.Inconjunctionwithlawreactorpressure low Water level inches) above top of initiates core spray and LPCI. active fuel (5)

2. In conjunction with high dry-well pressure, 120 sec, time delay, and low pressure core coolin0 interloct initiates auto blowdown.
3. Initiates HPCI and 5BG15,
4. Initiates starting of diesel generators.

2 High Drywell Pressure less than or equal to

1. Initiates core spray LPCI, HPCl, and SBC15.

(2). (3) 2 PSIG

2. In conjunction with low low watet level 120 sec. time 6; lay and low pressure core cooling interlock initiates auto blowdown.
3. Initiates starting of diesel generators.

1-Reactor Low Pressure Greater than or equal

1. Pereissive for opening core spray and LPCI to 300 PSIG & less a m in ion valves, f

than or equal to.

2. In conjunction with low low reactor water 350 P5]G 1evel initiates core spray and LPCI.

1 )(4) Containment Spray Interlock Creater than or equal Prevents inadvertent operation of containment 2/3 Core height to 2/3 core height spray during accident conditions. ~2(4), Containment High Pressure Greater than or equal Prevents ir. advertent operation of contel ment to 0.5 PSIG & less spray during accident conditions. than or equal to 1.5 P51G j. l' Timer Auto Blowdown less than or equal to In conjunction with low low reactor water 120 seconds level, high dry-well pressure and low - I pressure core cooling interlock initiates auto blowdown. i~ 2 Low Pressure Core Cooling Greater than or equal Defers APR actuation pending confirmation of l Piano Discharge Pressure to 50 PSIG & less low pressure core cooling systee operation. h than or equal 100 P5]G 2/ Bus 4 KV Loss of Voltage Trip on 2930 volts

1. Initiates starting of diesel generators.

p isergerzy Buses plus or sinus 55

2. Permissive for starting (CCS pumps.

decreasing voltage

3. Removes nonessential loads from buses.
4. Trips emergency bus normal feed breakers.

2 Sustained High Reactor less than or equal to Initiates isolation condenser. Pressure 1070 PSIG for 15 l seconds 2/ Bus . Degraded Voltage on 4 KV Greater than of equal to Initiates eiere and picks up time delay g leergency Buses 3708 volts (equals 3784 relay. Diesel generator picks up load if v volts less 25 tolerance) degraded voltage not corrected after time after less than or equal delay, to 5 minutes (pivs 55 tolerance) with a 7 sec-ond (plus or sinus 205) icherent time delay hotes: (See next page) 3/4.2 10 g

m C l ') 4 DRESDEN II DPR-19 Amendment No. 108 3.2 LIMITING CONDITION FOR OPERATION BASES (Cont'd.) For effective emergency core cooling for small pipe breaks,.the HPCI system must function since reactor pressure does not decrease . rapidly enough to allow either core spray or LPCI to operate in . time. The automatic pressure relief function is provided as a backup to the HPCI in.the event the HPCI does not operate. The arrangement of the tripping contacts is such as to provide this -function when necessary and minimize spurious operation. The trip i settings given in the specification are adequate to assure the above criteria are met (Ref. SAR Section 6.2.6.3). The specification preserves the effectiveness of the system during periods of maintenance, testing or calibration and also minimizes the. risk of inadvertent operation; i.e., only one instrument channel out of service. L Two radiation monitors are provided on the refueling floor which l initiate isolation of the reactor building and operation of the l standby gas treatment systems. The trip logic is one out of two. Trip settings of less than or equal to 100 mR/hr for the monitors on the refueling floor are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident-leaves the reactor building via the normal ventilation stack but that all the activity is processed by the standby gas treatment system. The~ instrumentation which is provided to monitor the post accident condition is listed in Table 3.2.6. The instrumentation listed I and the limiting conditions for operation on these systems ensure L adequate monitoring of the containment following a loss-of-coolant l accident. Information from this instrumentation will provide the operator'with a detailed knowledge of the conditions resulting I from the accident. Based on this information he can make logical . decisions regarding post accident recovery. .The specifications allow for post accident instrumentation to be out of service for a period of 30 days. This period is based on the fact that several diverse instruments are available for guiding the operator should an accident occur, on the low probability of an instrument being out of service ana an accident occurring in the 30-day period, and on engineering judgment. The radioactive liquid and gaseous effluent instrumentation is provided to monitor the release of radioactive materials in liquid L and gaseous effluents during releases. The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of 10 CFR 20. l The relay setting for 4KV emergency bus loss of voltage is chosen to give positive indication of the need to start the diesel generator, B 3/4.2-33

IC. DRESDEN II DPR-19 Amendment No. 108 3.2 LIMITING CONDITION FOR OPERATION BASES (Cont'd.) without being affected by normal voltage fluctuations due to pumps starting. Reset of the relay, approximately 11% above the trip point, indicates that the diesel generator has restored bus voltage and will accept ECCS loads. The' reset signal provides a permissive for starting ECCS pumps. The setting for 4KV emergency bus degraded voltage is chosen to detect sustained degraded voltage which may cause equipment damage, while preventing trips caused by voltage fluctuations. The reset point for degraded voltage indicates restoration of normal bus voltage. 1 l L I V B 3/4.2-33a

y y .c. 'l ] ' Mm,w %,, 4 UNITED STATES - l' ~ 7, _ %= g. NUCLEAR REGULATORY COMMISSION - y WASHINGTON, D C. 20$55 11 COMMONWEAtTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 103 License No. DPR-25 1. The Nuclear Regulatory Comission (the Commission) has found.that: A. The application for amendment by the Commonwealth Edison Company (thelicensee)datedMarch 28, 1988 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 I; .B. The facility will o)erate'in conformity with the application, l the provisions of tie Act and the rules and regulations of the Comission; C. Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be l 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 Comission's regulations and all applicable requirements have been satisfied, h t

niu 7,z 2 2. Accordingly, the license is-amended by changes to the Technical. Specifications as indicated in the attachment to this license amendment and paragreph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows: t B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 103 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. I FOR THE NUCLEAR REGULATORY COMMISSION I 9 (f / $k ~ Q, ' John W. Craig, Director l Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Attachment:

L Changes to the Technical 'i Specifications Date of Issuance: flovember 21, 1989 i o L 3 l l l

l l ATTACHMENT TO LICENSE AMENDMENT-NO. 103 FACILITY OPERATING LICENSE DPR-25 DOCKET NO. 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 3/4.2-10 3/4.2-10 i l-B 3/4.2-33 B 3/4.2-33 B 3/4.2-33a ~ l 1 I l t l 1

rw _ 3 .s-L,,' 14 I i 5 e t .4 DRE5Dth lll DPb25. Amenement ho 103 1ABLE 3.2.2 IN51RUMENIA1]DN THAL INITI ATES OR CONTROLS lHE CORE AND CONIAllMEN1 COOLING SY51FM5 - o . Min. Nu. of Operable Inst. Channels per .1rio System (1) Trio Function Trip level Settino Remarks 2' (2) ' Reactor Low 84" (plus 4, minus 0 3. It conjunction with low resctor pressure Low Water Level inches) above top of initiates core spray and LPCI. active fuel (5) 2. In conjunction with high dry well ' pressure, 120 sec. time delay, and low pressure core cooling interlock initiates auto blowdown. 3. Initiates HPCI and SBG15. 4 Initiates starting of diesel generators. 2 High Drywell Pressure less than or equal to 1. Initiates core spray LPCI, HPCI, and 56G15. (2), (3) 2 PSIG 2, in conjunction with low low water level 120 sec, time delay and low pressure core cooling interlock initiates auto blowdown. 3. laitiates starting of diesel generators. .3 Reactor Low Pressure Greater than ce equal 1. Permissive for opening core spray and LPCI to 300 PSIG & less adelssion valves. than or equal to 2. In conjunction with low low reactor water 350 PSIG level initiates core spray and LPCI. 1(4) Containment Spray Interlock Greater than or equal Prevents inadvertent operation of con-2/3 Core Height ' to 2/3 core heignt tainsect spray during accident conditions. 2(4). . Containment High Pressure Greater than or equal ents inadvertent operation of con-to 0.5 PSIG & less ent spray during accident conditions than or equal to 1.5 PSIC I 1 liner Auto Blowdown Less than or equal to in conjunction with low low reactor water 120 seconds level, high dry well pressure and low pressure core cooling interlock initiates auto blowdown. l Defers APR actuation pending confirmation of 2 Low Pressure Core Cooling Greater than or equal Pump Discharge Pressure to 50 PSlG & less low pressure core cooling systee operation, than cr equal 100 PSIG l 2/ Bus 4 KV Loss of voltage Trip on 2930 volts 1. Initiates startir.g of diesel generators. l Emergency Buses plus or minus 53 2. Permissive for starting ECCS pumps. decreasing voltage 3. Removes nonessential loads free buses. 4 Trips emergency bus normal feed breakers. -r 2 Sustained High Reactor less than or equal to Initiates isolation condenser. Pressure 1070 PSIG for 15 seconds 2/ Bus Degraded voltage on 4 KV Greater than or equal Initiates alare and picks up time delay Emergency Buses to 3708 volts (eouais relay. Diesel generator picks up load if 3784 volts less 2% toler-degraded voltage not corrected after time l ance) after less than or delay. equal to 5 minutes (plus 5% tolerance) with a 7 second (plus or minus 20%) inherent time delay hotes: (See next page) 3/4.2-10 - ~-.

em n g3- - +. DRESDEN III DPR-25 Amendment No. 103 i r

3. 2 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)-

For effective emergency core cooling for small pipe breaks, the HPCI .. system must function since reactor pressure does not decrease rapidly t' enough to allow either core-spray or LPCI to operate in time. The auto-matic pressure relief function is provided as a backup to the HPCI in the event the HPCI does not operate. The arrangement of the tripping contacts is such as to provide this function when necessary and minimize spurious operation.. The trip settings given in the specification are adequate to assure the above criteria are met. (Ref. Section 6.2.6.3 SAR.) The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the' risk of inadvertent operation; i.e., only one instrument channel out of service. Two radiation monitors are provided on the refueling floor which initiate l e isolation of the reactor building and operation of the standby gas treat-i ment systems. The trip logic is one out of two. Trip settings of less than or equal to 100 mR/hr for the monitors on the refueling floor are based upon initiating normal ventilation isolation and standby gas treat- -ment. system operation so that none of the activity released during the refueling accident leaves the reactor building via the normal ventilation stack but that all the activity is processed by the standby gas treat-ment system.

The instrumentation which is provided to monitor the post accident condi-tion is listed in Table 3.2.6.

The instrumentation listed and the limiting conditions for operation on these systems ensure adequate monitoring of the containment following a loss-of-coolant accident. Information from this. instrumentation will provide the operator with a detailed knowledge of the conditions resulting from the accident. Based on this information he can make logical decisions regarding post accident recovery. The specifications allow for post accident instrumentation to be out of service for a period of 30 days. This period is based on the fact that several diverse instruments are available for guiding the operator should an accident occur, on the low probability of an instrument being out of service and an accident occurring in the 30-day period, and on engineering . judgment. The radioactive liquid and gaseous effluent instrumentation is provided to j monitor the release of radioactive materials in liquid and gaseous effluents during releases. The alarm setpoints for the instruments are provided to ensure that the alarms will occur prior to exceeding the limits of 10 CFR 20. The relay setting for 4KV emergency bus loss of voltage is chosen to give positive indication of the need to start the diesel generator, without being affected by normal voltage fluctuations due to pumps starting. B 3/4.2-33

1. N DRESDEN Ill DPR-25 Amendment No.103 3.2 LIMITING CONDITION FOR OPERATION BASES (Cont'd.) t-Reset of the relay, approximately 11% above the trip point, indicates that the diesel generator has restored bus voltage and will accept ECCS Loads. The reset signal provides a permissive for starting ECCS pumps. I The' setting fo* 4KV emergency bus degraded voltage is chosen to detect . sustained degraded voltage which may cause equipment damage, while pre-venting trips caused by voltage fluctuations. The reset point for degraded voltage indicates restoration of normal bus voltage. i i B 3/4.2-33a L}}

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