|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc ML20078E2051995-01-20020 January 1995 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20078Q6061994-12-12012 December 1994 Proposed TS Section 3.4/4.4 Re Standby Liquid Control Sys ML20064J3181994-03-11011 March 1994 Proposed Tech Specs Re Snubber Visual Insp Intervals ML20059A7321993-12-20020 December 1993 Proposed Tech Specs 1.1/2.1-1 Increasing MCPR Safety Limit from 1.06 to 1.07 for Units 1 & 2 ML20059A8301993-10-21021 October 1993 Proposed Tech Specs Deleting Requirements for Demonstrating Operability of Redundant Equipment When ECCS Equipment Is Found Inoperable or Made Inoperable for Maint ML20125D6381992-12-0808 December 1992 Proposed Tech Specs 3/4.1 Re Reactor Protection Sys ML20116J7091992-11-0606 November 1992 Corrected Proposed TS 3.2/4.2-8 Re Administrative Changes ML20106A6221992-09-15015 September 1992 Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits ML20099D7791992-07-29029 July 1992 Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity 1999-08-13
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217D7961999-10-12012 October 1999 Proposed Tech Specs Pages,Removing Turbine EHC Low Oil Pressure Trip from RPS Trip Function Requirements in TS Sections 2.2 & 3/4.1.A ML20210R8281999-08-13013 August 1999 Revised Bases Page B.3/4.9-6 to TS Section 3/4.9,providing Clarity & Consistency with Sys Design Description in UFSAR Sections 8.3.2.1 & 8.3.2.2 ML20209J2321999-07-16016 July 1999 Proposed Tech Specs 3/4.7.D Replacing Limit for Any One Msli Valve of Less than or Equal 11.5 Sfch with Aggregate Value of Less than or Equal 46 Scfh for All MSIVs ML20196K1941999-06-30030 June 1999 Rev 2.0 to Chapter 11 of Quad Cities Offsite Dose Calculation Manual ML20209C2951999-06-29029 June 1999 Proposed Tech Specs Section 3/4.3.C, Reactivity Control - Control Rod Operability ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205L2631999-04-0505 April 1999 Tech Spec Page B 3/4.5-2 to TS Section 3/4.5, ECCS, to Clarify Requirement Discussed in ML20205J9741999-03-30030 March 1999 Proposed Tech Specs,Deleting Various License Conditions That Have Been Completed,Making Editorial Changes & Providing Clarifying Info ML20205J9321999-03-30030 March 1999 Proposed Tech Specs 3/4.6.E Changing SRs 4.6.E.2 to Allow one-time Extension of 18 Month Requirement to Pressure Test or Replace One Half of MSSVs to Interval of 24 Months ML20205J9911999-03-30030 March 1999 Proposed Tech Specs Allowing Alternative Methodology for Quantifying RCS Leakage When Normal RCS Leakage Detection Sys Is Inoperable ML20199L6921999-01-21021 January 1999 Proposed Tech Specs Section 3/4.6.I,relocating from Chemistry TS Requirements to UFSAR ML20199L7741999-01-21021 January 1999 Proposed Tech Specs Bases for Sections 3/4.10.K & 3/4.10.L, Provides Description of Design & Operation of RHR SD Cooling Subsystem ML20196H4571998-11-30030 November 1998 Proposed Tech Specs 3/4.8.J, Safe Shutdown Makeup Pump, Reducing Current AOT from 67 Days to 14 Days ML20196F6451998-11-30030 November 1998 Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document ML20196K5861998-11-0505 November 1998 Rev 3 to Qcap 0280-01, Process Control Program for Processing of Radioactive Wet Wastes at Quad Cities Nuclear Power Station ML20155D8091998-10-29029 October 1998 Proposed Tech Specs Bases Sections 3/4.2.D & 3/4.5.D, Providing Clarity & Consistency with Sys Design Description Contained in UFSAR Section 5.4.6.2 ML20195J9041998-09-24024 September 1998 Rev 0 to TR-VQ1500-02, Clean ECCS Suction Strainer Head Loss Test Rept ML20151S7991998-08-31031 August 1998 Proposed Tech Specs,Increasing Max Allowable MSIV Leakage from 11.5 Scfh to 30 Scfh Per Valve When Tested at 25 Psig, IAW SR 4.7.D.6 ML20236W8401998-07-31031 July 1998 Proposed Tech Specs Bases 3/4.7.C & 3/4.7.12.C,clarifying Testing Requirements for Primary Containment Excess Flow Check Valves ML20247D7761998-05-0505 May 1998 Proposed Tech Specs Page B 3/4.4-1,changing Administrative Error.Bases for Net Quantity of Gallons for Solution Is Changed from 3254 (Correct Quantity) to 3245 ML20246Q3481998-04-29029 April 1998 TS Page B 3/4.5-3,reflecting Change to TS Bases for Section 3/4.5.C ML20217G1481998-03-27027 March 1998 Proposed Tech Specs Bases Section 3/4.5.A,reflecting Design Info Contained in Rev 4 to Ufsar,Dtd Apr 1997 ML20216C6381997-08-29029 August 1997 Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates ML20196G0271997-05-0101 May 1997 Proposed Tech Specs 4.9.A.8.b Revising Load Value for Diesel Generator to Be Equal to or Greater than Largest Single Load & Revising Frequency & Voltage Requirements During Performance of Test ML20138G3321997-04-29029 April 1997 Proposed Tech Specs,Permitting Loading of ATRIUM-9B Fuel in Plant Unit Core for Operational Modes 3,4 & 5.Modes Will Support Refueling Activities Such as Fuel Load,Vessel re- Assembly & Single Rod Timing ML20138B3231997-04-21021 April 1997 Proposed Tech Specs,Requesting That NRC Grant Exigent Amend to TS 2.1.B & 6.9.A.6.b to Support Plant Unit 2 Cycle 15 Operation Scheduled to Begin 970519 ML20137G3981997-03-26026 March 1997 Proposed Tech Specs 3/4.7.P Re Standby Gas Treatment & TS 5.2.C Re Secondary Containment ML20135F7321997-03-0303 March 1997 Proposed Tech Spec Bases 3/4.9.E,clarifying Purpose of SR 4.9.E ML20135D9461997-02-24024 February 1997 Proposed Tech Specs,Clarifying Bases for TS Surveillance 4.8.D.5.c ML20138L4011997-02-17017 February 1997 Proposed Tech Specs Section 2.1.B Re Thermal Power,Section 3/4.11 Re Power Distribution Limits,Section 3/4.6 Re Primary Sys Boundary,Section 5.3 Re Reactor Core & Section 6.9 Re Reporting Requirements ML20138L3701997-02-17017 February 1997 Proposed Tech Specs 4.9.A.8.h Re Diesel Generator Endurance Test Surveillance Requirements ML20134D2191997-01-27027 January 1997 Proposed Tech Specs Deleting marked-up Sentence from TS Bases for Section 3/4.7.K ML20129K3321996-10-18018 October 1996 Cycle 15 Startup Test Results ML20129C2391996-10-16016 October 1996 Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage ML20129D3981996-09-20020 September 1996 Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases ML20216H8841996-06-30030 June 1996 Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F ML20116F3971996-06-30030 June 1996 Rev 1.8 to ODCM, Annex,Chapters 10,11,12 & App F ML20113C3571996-06-25025 June 1996 Proposed Tech Specs Re Upgrade Program ML20113A7861996-06-10010 June 1996 Proposed Tech Specs,App A,To Reflect Transition of Fuel Supplier from General Electric to Siemens Power Corp ML20117D7121996-05-0606 May 1996 Proposed Tech Specs,Implementing New LCO & SR Re Revs to TS for 10CFR50,App J,Lrt ML20107A1881996-04-0404 April 1996 Proposed Tech Specs 3.4/4.4 Re Standby Liquid Control Sys ML20101H1381996-03-25025 March 1996 Complete Version of TS Upgrade Program Pages That Reflect Current Configuration of Plant & Specifies SRs That Will Not Be Current Upon Implementation of Tsup Project ML20097D9231996-02-0808 February 1996 Proposed Tech Specs,Upgrading Existing TS 3/4.5, Eccs ML20100C0441996-01-24024 January 1996 Secondary Containment Leak Test Summary ML20093K7721995-10-12012 October 1995 Quad-Cities Nuclear Power Station Unit 2 Cycle 14 Startup Test Results Summary ML20098A3821995-09-20020 September 1995 Proposed Tech Specs,Revising TS Upgrade Program & Improving Plant Submittals ML20086D4741995-06-30030 June 1995 Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2 ML20087H8651995-05-0202 May 1995 Proposed Tech Specs Re TS Upgrade Program Section 3/4.10 ML20082H7481995-04-10010 April 1995 Proposed Tech Specs,Revising SR for HPCI & RCIC Sys ML20080K8171995-02-23023 February 1995 Proposed Tech Specs,Changing Name of Iige to Reflect Results of Merger Between Iige,Mid American Energy Co,Midwest Power Sys Inc & Midwest Resources Inc 1999-08-13
[Table view] |
Text
- - _ - - _ - -
QUAD-CITIES DPR-29 3.11/4.11 HIGH ENERGY PIPING INTEGRITY
, (OUTSIDE CONTAINMENT)
HITING COND1110NS FOR OPERATION SURVEILLANCE REQulREMENTS App cability: Applicability:
Applie to operating status of certain Applies to the periodic examination
' piping o. side primary containment, requirements for certain piping o side primary containment.
Objective: Objectivc:
To assure the in grity of sections of To determine the condit n of the sec-piping which is po tulated to effect safe tions of piping.
plant shutdown.
SPECIFICATIONS The high energy piping sec ions identi- The inspect' ns listed in lible 4.11-1 fied in Table 4.11-1 shall maintained shall be 'rformed as speci'ied, free of visually observable t ough wall leaks.
J
- 1. If a leak is detactad by e surveillance program of Sp ifi-cation 4.11, efforts to iden) fy the source of the leaks shall s started immediately.
- 2. If the source of leakage nnot be identified within 2 ours of detection or if the 19 is found to be from a eak in the piping sections i ntified in Table 4.11-1, t pressure with-in the sectio of piping shell be brought atmospheric pres- 3 sure with 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. ?
- 3. When e modifications identi-fie in Commonwealt's Edison's 1 .ter to the NRC caled 7D.eptember 16, 1975 (G. Abrell to Ziemann) have been completed, Technical Specifications 3.11 and 4.11 will no longer be required.
3.11/4.11-1 Amendment No. 114 9109060053 910929 PDR ADOCK 030002S4 P PER
f(
1 l
QUAD-CITIES- !
-OPR-29
'3. . 11 BASES l Intensive analys ._ review has shown that there are specific postulat Mtfi" energy piping system fa which have the potential to inhib cold shutdown of tha r . .
This cinchQon is based on-ng the basic NRC
.. Lhigh energy line L ::riteria.- To redo ability of such failures, P -- certain plant modif. .aions-are nec . Unt e modifications are comple'.a. additional surv Sela
~
will be performed.duri ant operation to enhance the~ deteJeserC. piping system defects. The inservice ation and
- the fre eney15T inspection-will provide a means for timely detection o j defects.
l-i j-I I-4 t
+
4 h
3.11/4.11-2 Amendment No. 114 e
- e i,+ - - .+.m. ~-,~,.s, ....,,m.,-m...------,-e --.-....-m,- -,,-_,.1-- +.-,w ..~-,v--.
- - . ., ,-,,-v- em -
.- .l QUAD-CITIES DPR-29 I TABLE 4.11-1 -I SURVEILLANCE REQUIREMENTS FOR HIGH ENERGY PIPINC OUTSIDE CONTAINME Piping Surveillance !
Survelliance Area Technique frequencJ ',
14ain Steam from primacy containment penetration to secondary Visual (3) 0 days- .!
containment penetration
. l 6
Reactor Feedwater rom primary containment ;
Piping- .p etration to secondary j
con n t penetration Visu 30 days -
and "A reactor feed t pump disc ge to the 24-inch
HPCI Steam Piping i From the primary c nment ;
penetration to th e tor Visual (3) 30 days >
building penet ion RCIC Steam Piping. From pr ry containment !
pene y ine.
tion to the RCIC \ ual(3)
Q 30 days-i
~
N ;
Notes: i
[1] Visual ervation of piping insulation and area for evidence of wetnes or any '
phys I damage resulting from a leak. Surveillance to be performed using ormal ess without scaffolding or-any other access aids. i L j 2) "A" Reactor feed pump-for Unit 1 "C" Reactor feed pump for Unit 2. ;
l- !
l' .
l l !
I e
I l :
! '[
i-1 I
3.11/4.11-3 Amendment No. 114 I
)
h i
, , . , . , , . . . , . , . ...-.,,c,.
c:
s J'
[.:.
~
SIGNIFICANT HAZARDS CONSIDERATIONS AND ENVIRONMENTAL ASSESSMENT EVALUATION ,
Proposed Deletion of 'TS 3.11/4.1.1
'HIGH . ENERGY PIPING INTEGRITY" l:
EVAI,UATION ZQB SIGNIFICANT HAZABDJ CONSIDERATION PROPOSED DELETION OF SPECIFICATION 3.11/4.11 HIGH ENERGY PIPING INTEGRITY t
The proposed changes provided in this amendment request are made in order to delete requirements in the Technical specifications that are no longer in effect. These changes have been reviewed by Commonwealth Edison Company and we believe that they do not present a Significant Hazards Consideration. The basis for our determination is documented as follows:
BASIS EQB HQ SIGNIFICANT HAZARDS CONSIDERATION !
Commonwealth Edison has evaluated this proposed amendment and determined that it involves no significant hazards consideration.
In accordance with the criteria of 10 CFR 50.92(c) a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility, in accordance with the proposed amendment, would not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated, because:
Present Section 3.11/4.11, High Energy Piping Integrity !
(Outside Containment), was a temporary addition to the Quad Cities Technical Specifications and was intended to be deleted when modifications were made to the affected high energy piping systems. Since required modifications were completed in 1979, the proposed deletion of Section 3.11/4.11 is an administrative removal of requirements that are no longer applicable. Due to the administrative nature of the proposed change it cannot involve a significant increase in the probability or t'asequences of an accident previously evaluated.
- 2) Create the possibility of a new or different kind of accident
- from any previously evaluated because:
The proposed change deletes temporary requirements that are no longer applicable and are not being used at Quad Cities '
Nuclear Station. The modifications to the piping systems to address high energy line breaks outside containment were reviewed and approved by the NRC prior to installation and were designed to meet or exceed applicable design codes and ,
standards. Since this change dclctes temporary provisions thr.t are no longer applicable, 't cannot create the possibility of a new or different kind of accident from any l previously evaluated.
- 3) Involve a significant reduction in the margin of safety because:
i
\
f/
e*~
c .
c
,4, at
- The--deletion of the temporary provisions of Section-3.11/4.11- ,
- upon completion of acceptable. modifications, follows NRC i
guidance in the NRC letter dated March 8,--1976,-that '
authorized issuance of Amendments 24 and 23=to Quad Cities:
Units:1 and'2,-respectively. The-piping modifications were- -
- approved.:by the NRC prior to installation and tho-installation was-made in accordance-with approved design change documentation. - Since the proposed change deletes temporary provisions-that are no longer applicable, it cannot involve a significant reduction in any margin of safety.
1 4
4 4
f
-l c
h wy-, 4w .+, p - --wwa-ve,,*c-,ew- e w g , I w w g s we --rw,, erg,e,v--n.pe-, . - ~e+,,m-,v-~ ewg op.,, ,,---a-=.r r - , e w,-- ew-- <em - - ,a,~ow ,N,-- o-we - --,-c ~= ----**
- EHLT_BqHHHHTAL AREEEEliEXT EVALUATIOH PROPOSED SPECIFICATION-SECTION 3.11/4.11 HIGH ENERGY PIPING INTEGRITY Commonwealth Edison has evaluated the proposed amendment in accordance with the requirements of-10 CFR 51.21 and has determined that the amendment meets the requirements for
Commonwealth Edison has determined that the amendment involves no significant hazards consideration, there are no significant change in the types or significant increase in ;
the amounts of any effluent that may be released offsite, and there .is no significant increase in individual or-cumulative occupational radiation exposure.
The proposed amendment does not modify the existing facility and doos not involve any new operation of the plant.
As such, the preposed amendment does not involve any change in the type or significant increases in effluents, or increase individual or cumulative occupational radiation exposure. The deletion ut Section 3.11/4.11 "High Energy .
Piping Tntegrity'* does not impact the safe operation of the !
plant since the curveillances required by the specification have been discontinued in response to thu installation of modifications, ac provided for in the Technical Specification. ;
t 9
F 1
W P
4 i
i
44.'
= _;f s
h l L 1
e
-- - a, QC-1/ QC-2 DIFFERENCES l 1 f
i
-)
e -
a b
--TS 3,11/4.11 y
-t
'HIGH ENERGY PIPING INTEGRIT-Y'- :
t
-I i
~;
-l
- 5 i
t
?
I
?
' I I
l l'
i i
a i
, . . . . . . ..-.,ry..ys.. ,-..,w.,_e,,,,,w.,_, ,y e . ,w_..m .:,,,, ,. , ...,-,_.+r. . ..y4._,,,,,.~,....,,m.-.#,< ~ - y% -,- ,. .-..~m._ . _ + , . . .. ..~..---.sa
1.
s
.; E +
8 COMPARISON OF.. UNIT 11MRD UNIT 2 TECHNICAL BPECIFICATIONS FOR THE i IDENTIFICATION OF-TECHNICAL' DIFFERENCES' l
.SECTION:3.11/4.11
. :i HIGH ENERGY PIPING INTEGRITY :
=t Commonwealth Edison'has conducted a comparison review of '
the Unit'l and Unit-2 Technical Specifications to identify :
, any technical differences in support of combining the
. Technical Specifications:into one. document. The intent of the review was not to identify any differences in *
.prese.itation style-(e.g. table formats, use.of capital
' letters, etc.)?or punctuation but rather-to identify creas !
which the Technical. Specifications are technically different. i The: review of Section- 3.11/4.11, "High Energy Piping k
- Integrity did not reveal any technical or administrative ;
differences.
P
?
f
~
.- t 3
s k
I l
t i
8
.i 3
d S
[N . - - . . . . - . . , . , . - - - . . . . _ . . _ . . -