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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
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METROPOLITRI EDISCN CC G EIY JERSEY CE'I~'RAL PCWER & L.91r" COMPANY XiD PEI'iSYL7NiIA FJ '"TRIC CCIGA iY THREE M'LE ipa'iL SUCLFAn )TATION UNIT 1 Oper, ing License No. DPR-50 Docket :io. 5c-269 Technical Specificatien Change Pecuest No. 7h This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Cperating License No. DFR-50 for Three Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.
METROPOLITAN EDISON COMPANY l
By /
lic6 President N Sworn and subscribed to me this / 3 day of /Y , 1978.
a/ n cu Notary Phbli6
. "m Je GECRGE J.TROFFER Notary Pub;ic, Reading, Berks Co.
My Ccmm!ssicn Expires Jan. 25,19S2
$91108o 660 1584 038
UITITED STATES CF AEICA IiUCLEAR REGULATCRY CCMMISSICN IN THE MA71'IR OF DOC ET N0 50-2c9 LICE:ISE N0. DPR-50 METROPOLITA'I EDISON COMPA!IY This is to certify that a copy of Technical Specification Change Request No.
Th to Appendix A of the Operating License for Three Mile Island :Iuclear Statien Unit 1, has, en the date given below, been filed with the U. S. Nuclear Regulatory Cec =ission and been served en the chief executives of Lcndenderry Tcvnship, Dauphin County, Pennsylvania and Dauphin Ccunty, Pennsylvania by deposit in
- the United States = ail, addressed ac fo11cvs:
Mr. 'Jeldon B. Arehart Mr. Harry B. Reese, Jr.
Board of Supervisors of Board of County Cen=issioners Londonderry Township of Dauphin Count'/
R. D. #1, Geyers Church Road Dr.uphin County Ccurt House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON COMPANY
/
/ .
By / ~
Vice President Dated: March 13. 1o78 1584 039
7 N
Three l411e Island Nuclear Station, Unit 1 0;erating License No. OPR-50 Docket No. 50-289 Technicsl Scecification Chance Request No. 7h The licensee requests that the attached changed page replace page k-kl of the existing Technical Specifications, and that the attached page 3-18e be added to the existing Technical Specifications.
R6asons for Chance Rec _uest -
This change was requested by the Cen=1ssion in their' letter of Novenber 11,
~
1977 The Cc==ission requires specifications identifying the RC overpressurizatien syste= enabling te=perature and the pcVer operated relief . valve (PORV) setpoint ,
and specifications relating to syste= testing and maintenance. -
- , . ~ - _.. . _ . _ _ _,.. ._..._,.._m . . . _ _ .
Safety Analysis Justifyine Chance , - . _ ;,
This change _ increases the specifications required.to be followed to take the electrc=atic relief valve (ERV), out of service, states the settings for the-
'ERV, and defines operating' restrictions for the EPI valves and' the pressurizer level. (1). Therefore, the probabilit7 Sf occurrence or the consequences of an accident or =alfunction of equip =ent t=portant to safety previously evaluated in the safety analysis report is not increased; (ii) the possibility of an accident or =alfunction of a different type than any evaluated previously in the safety analysis report is not created; (iii) the =argin of safety defined in the basis for any technical specification is not reduced.
i
h.3.2 DIERGE' ICY CORE . SOLI:IG SYSTDI Ac711cchility Applies to periodic testing require =ent for e=ergency core ecoling systems.
Objective To verify that the e=ergency core cooling syste=s are operable.
S;ecifict- en g"D<D(( ^D D\fk 3 6w 6 .} . -
L.5.2.1 High Pressure Injection
- a. During each refueling interval and following =aintenance or
=odification that affects system flow characteristics, system 61A pumps and system high point vents shall be vented, and a systen test shall be conducted to de=enstrate that the systes is operable,
- b. After a satisfactory test of the emergency loading sequence !
(h.5.1), the M. U. Pu=p and its required supporting auxiliaries vill be started =anually by the operater and a test signal vill be applied to the high pressure injection valves MU-V16A, B, C, D to de=cnstrate actuation of the high pressure injection 61A system for emergency core cooling operatien. .
The test vill be considered satisfactory if the valves have l cc=pleted their travel and the M. U. pu=ps are running as evidenced by the control board component operating lights.
Mini =un acceptable flev must be greater than or equal to 200 g;n per injection leg and greater than or equal to 500 g;= per HPI pu=p. 61A
- c. The correct limit switch setting of MU-716A, B, C, D will be verified within four hours of any =aintenance en the valve or operator that affects the limit switch setting, when the High Pressure Injection System is required to be operable.
- d. Testing which requires HPI flev thru MJ-V16A/3/C/D shall be cen-ducted only under either of the following conditions:
- 1) T avg. shall be greater than 3200F.
- 2) Head of the Reactor Vessel shall be removed.
h.5.2.2 Lov Pressure Injection
- a. During each refueling period and folleving maintenance or mcdification that affects system flev characteristics, syst a pumps and high point vents shall be vented, and a systen test shall be conducted to de=onstrate that the system is operable.
The auxiliaries required for low pressure injection are all included in the emergency loading sequence specified in h.5.1.
- b. The test vill be considered satisfactory if the decay heat pu=ps listed in h.15.lb have been cuece:sfully started and the decay heat injection valves and the decay heat supply valves
.have ec=pleted their travel as evidenced by the centrol beard ec=ponent 0;cratinc lichts. "i-" acceptable flev must be
, L. '
greater than or equal to 2700 cpm per injection leg /LPI purp.
< - 1584 041
me a D D 3-)
F.lectrc=ath selief valve A
3'. : .12 oc olfu_ . .=
A;;' i :abilicy A;;11es to the settings, and conditions for isolation of the electrc=atic relief valve.
C': ,' e et ive Tc prevent the possibility of inadvertently over pressurizing the primary leop.
4 2;ecificatien 3 1.12. 1 The electrc=atic relief valve shall not be taken out of service,
-- rior shall it -be isolated frc= the .syste=- (e.tcept that the - . ...
-: electro =atic relief valve =ay be isolated to .li=it leakage to .
~~ ' ~ ~ ~~
~
. T - -- 1. . ,.. _ ~.EJO.yithin.3.heili=its.- of sneci.fication :3 1. 6 ) i unlem_cne of.he.. .
- 7. _. - - .-= . . . . .
~T TJJ11ollowing.dri-i.n. effect:- . . 2. .- .- . . . . .. .--=...._.T..__._-..1...____
-' - - . ~ '
- High Pressure Injec*! ion Pu=p break'ers are racked out.oi '". . - . .
- a. ~
'i' ~~ 'MU-V16A/3/C/D are closed.~
- -- - - - - :: ~- ' ~ ; - 5
. ~
- 2. - -7 ~ 7 -- n
.b . Head of the Reactoro Vessel is re=oved. --
- c. T avg. 'Is above 320 F. _ _ . __ ___i r 1 .] , , , - . _ ,
3.1.12.2 The electrc=atic relief valve settings shall be as follevs, within the tolerances listed in the bases of specification 3 1.2:
Above 275 F - 2255 psig Belev 275 F h85 psig 3.1.12.3 ' If the reactor vessel head is installed and T avg. is 12750F, High Pressure Injection Pu=p breakers shall not be racked in unless:
- a. MU-V16 A/B/C/D are closed, and
- b. Pressurizer level is 1 220 inches.
Bases If the electrc=atic relief valve is re=cved from service, sufficient measures are incorporated to prevent overpressurization by either eliminating the high pressure sources or flovpaths or assuring that the RCS is open to atmosphere.
,In order to prevent exceeding leakage rates specified in T.S. 3.1.6. the electrc=atic relief valve may be isolated.
Tne electrc=atic relief valve setpoints are specified with tolerances assumed in the bases for Tecnnical Specification 3 1.2.
5 ith 3CS te=peratures less than 2750 F and the =akeup pu=ps running, the high pressure injection valves are closed and the pressuriser level is maintained le: than 220 inches to prevent overpressurination in the event of any sing'.e fai;;re.
1584 042 2-uc .