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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C6321999-09-30030 September 1999 Proposed Tech Specs 3/4.17.B, Control Room Emergency Filtration Sys, Eliminating Unnecessary in-place Testing of HEPA & Activated Charcoal Filters Based on Sys Operating Time ML20203B3191999-01-28028 January 1999 Proposed Tech Specs Page 60d,incorporating Approved Amend 103 Changes for Use by NRC in Issuing SER ML20206P1331998-12-31031 December 1998 Proposed Tech Specs,Revising pressure-temp Limit Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4,deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR for SLCS ML20154L9551998-10-12012 October 1998 Proposed Tech Specs Re Rev of Statement on Normal Shift Length & Other Misc Changes ML20154L9041998-10-0909 October 1998 Proposed Tech Specs,Incorporating Proposed Changes Re Surveillance Test Interval/Aot Extension Program ML20153F0191998-09-25025 September 1998 Proposed Tech Specs Pages Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20236P5421998-07-0101 July 1998 Proposed Tech Specs Pages 30,50 & 53 Containing Administrative Changes Re Power Rerate Program ML20249C5121998-06-19019 June 1998 Proposed Tech Specs Pages Re Rev 2 to 960726 LAR to License DPR-22,to Establish TS Requirements That Are Consistent W/Analysis Inputs Used for Evaluation of Radiological Consequences of MSLB Accident ML20247K6341998-05-12012 May 1998 Proposed Reprinted Tech Specs Bases Pages,Containing Spelling & Grammatical Corrections ML20216D0021998-03-19019 March 1998 Proposed Tech Specs,Providing Consistent Wording Throughout TS & Providing Sound Basis for Frequency of Actions Required Each Shift ML20248L2001998-03-13013 March 1998 Proposed Tech Specs Revising SLMCPR ML20248L4101998-03-0606 March 1998 Revised Page 39 to Proposed TS Change ML20202H7061997-12-0404 December 1997 Proposed Tech Specs Increasing Plant Max Power Level from 1670 Mwt to 1775 Mwt ML20203A9771997-11-25025 November 1997 Proposed Tech Specs Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20211J9801997-09-29029 September 1997 Proposed Tech Specs Page 249b & Cleaned Typed Page 249b, Adding Footnote to Topical Rept NEDE-24011-P-A Stating That Topical Rept Is Approved for Cycle 18 Only ML20210Q2971997-08-21021 August 1997 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20141B9181997-06-19019 June 1997 Proposed Tech Specs Re Update of Design Basis Accident Containment Temp & Pressure Response ML20137W2201997-04-11011 April 1997 Proposed Tech Specs 3.6.C Re Coolant Chemistry & TS 3/4.17B Re Control Room Emergency Filtration Sys ML20149M7281997-01-23023 January 1997 Proposed Tech Specs 3.5/4.5.C of TS Bases Describing Min RHR & RHRSW Pump Requirements for Post Accident Containment Heat Removal & Submit Update to Design Basis Accident Containment Temp & Pressure Response ML20132C6531996-11-25025 November 1996 Proposed Tech Specs,Sections 2.1.A Re SLMCPR & 3.11.C Re Olmcpr.Changes Revise SLMCPR Values & Deletes Sentence Re OLMCPR Limit Penalty for Single Recirculation Loop Operation ML20117A1551996-08-15015 August 1996 Proposed Tech Specs Re Revision to TS Administrative Controls Section 6.1.F.1 Stating That Either 8 or 12 H Shifts Will Be Considered Normal & 40 H Will Be Considered Nominal ML20116G8951996-07-26026 July 1996 Proposed Tech Specs Increasing Max Power Level by 6.3% to 1,775 from 1,670 Mwt.Summary of Plant Mods for Power Rerate Implementation & Power Rerate Environ Evaluation Encl ML20116D8361996-07-26026 July 1996 Proposed TS Sections 3.6.C & 3/4.17.B Re Reactor Coolant Equivalent Radioiodine Concentration & CR Habitability ML20100Q3861996-03-0101 March 1996 Proposed Tech Specs Re Periodic Replacement of Containment Purge & Vent Valve Seat Seal ML20095J4341995-12-20020 December 1995 Proposed Tech Specs Re Main Steam Isolation & App J Leak Rate Test Requirements ML20095E7121995-12-11011 December 1995 Proposed Tech Specs,Removing TS SR 4.7.D.4 & Replaces Seat Seals for Drywell & Suppression Chamber Purge & Vent Valves Every Five Yrs ML20094M1981995-11-14014 November 1995 Proposed Tech Specs,Incorporating Requirements of Option B, Section Iii.A for Type a Testing (Primary Containment ILRT) ML20091K6821995-08-18018 August 1995 Proposed Tech Specs Section 3.7/4.7 SGTS ML20087J4251995-08-15015 August 1995 Proposed Tech Specs,Revising Max Individual MSIV Leak Rate Acceptance Criteria of 11.5 Scfh to Overall Criteria That Encompasses Four Main Steam Lines Into One Limit of 46 Scfh ML20086D8011995-07-0505 July 1995 Proposed Tech Specs Extending Surveillance Test Intervals & Allowable out-of-svc Times for Selected Instrumentation ML20085N0991995-06-22022 June 1995 Proposed Tech Specs Supporting Implementation of BWR Thermal Hydraulic Stability Solution ML20082N8711995-04-20020 April 1995 Proposed Tech Specs Re SBGTS & Secondary Containment ML20069J1061994-06-0808 June 1994 Proposed TS Re SGTS & Secondary Containment ML20065B6691994-03-28028 March 1994 Proposed Tech Specs Re Approved Analytical Methods for Developing Core Operating Limits Rept ML20065B6991994-03-28028 March 1994 Proposed Tech Specs Re Standby Gas Treatment Sys Initiation Instumentation ML20063C9941994-01-26026 January 1994 Proposed Tech Specs,Requiring Valves to Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA ML20062N8731994-01-0404 January 1994 Proposed Tech Specs 3.11, Reactor Fuel Assemblies & Bases Re Methodology for MCPR ML20059E6041994-01-0303 January 1994 Proposed Tech Specs,Revising Surveillance Requirement 4.6.E.1.a to Require Valves to Be Tested Per Section XI Inservice Testing Requirements of ASME Boiler & Pressure Vessel Code ML1132102881993-11-30030 November 1993 Proposed Tech Specs Re Removal of Chlorine Detection Requirements & Changes to Control Room Ventilation Sys Requirements ML20056E1081993-08-10010 August 1993 Proposed Tech Specs Providing Clarification of Sampling & Analysis Requirements,Updating Liquid Effluent Sampling & Requirements & Correcting Typographical Errors in TS Section ML20045G6091993-07-0707 July 1993 Proposed TS 4.0.d Re Recording Unidentified & Identified Leakage Rates & 3/6/4.6 Re Analyzing Grad Samples of Primary Containment Atmosphere Once Per 12 H ML20128M7191993-02-12012 February 1993 Proposed TS Increasing Minimum Core Spray Pump Flow to More Conservatively Account for ECCS Bypass Leakage Paths ML20237G2081987-08-14014 August 1987 Proposed Tech Specs,Eliminating Certain Requirements for Plant Mgt & Support Staff to Hold Current Senior Reactor Operator Licenses ML20065E2121982-09-24024 September 1982 Proposed Tech Specs Re Surveillance,Reactor Protection Monitoring Sys,Jet Pump Surveillance,Organization & Steam Line Area Temp Switch Deviation ML1129708531982-07-0202 July 1982 Proposed Tech Spec Changes Allowing Plant to Remain at Substantial Power Level W/One Recirculation Pump in Operation & Equalizer Valve Closed ML1129708181981-03-19019 March 1981 Proposed Revisions to Tech Specs,App A,Pages 26,89-90 & 213-14 for Reactor Protection Sys ML20024G6491978-08-16016 August 1978 Proposed Tech Specs Raising Permissible Setpoint of Eight Safety/Relief Valves Installed at Plant to 1,108 Psig ML20127H2171978-08-10010 August 1978 Proposed Tech Specs to Authorize Use of Partial Drilled Model of Fuel Type for Plant Future Use ML20024G7051978-03-21021 March 1978 Proposed Tech Specs Re Application of Partial Drilled Model for Analyzing Retrofit Fuel Design Scheduled to Be Installed in Plant Reactor in Fall 1978 Refueling Outage ML20024G7031978-03-20020 March 1978 Proposed Tech Specs Clarifying Certain Sections of Interim Radioactive Effluent Tech Specs 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C6321999-09-30030 September 1999 Proposed Tech Specs 3/4.17.B, Control Room Emergency Filtration Sys, Eliminating Unnecessary in-place Testing of HEPA & Activated Charcoal Filters Based on Sys Operating Time ML20211G0391999-02-10010 February 1999 Revised ODCM, Including Revs to Revised ODCM Index,Odcm 01.01 Page 2 Paragraph 1,ODCM 02.01 Page 2 Section 1.0,ODCM 05.01 Page 2 Sections 1.0,2.0 & 3.0 & ODCM 13.05 Page 2 ML20203B3191999-01-28028 January 1999 Proposed Tech Specs Page 60d,incorporating Approved Amend 103 Changes for Use by NRC in Issuing SER ML20206P1331998-12-31031 December 1998 Proposed Tech Specs,Revising pressure-temp Limit Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4,deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR for SLCS ML20154L9551998-10-12012 October 1998 Proposed Tech Specs Re Rev of Statement on Normal Shift Length & Other Misc Changes ML20154L9041998-10-0909 October 1998 Proposed Tech Specs,Incorporating Proposed Changes Re Surveillance Test Interval/Aot Extension Program ML20153F0191998-09-25025 September 1998 Proposed Tech Specs Pages Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20237E9771998-08-20020 August 1998 Rev 4 to EWI-09.04.01, Inservice Testing Program ML20236P5421998-07-0101 July 1998 Proposed Tech Specs Pages 30,50 & 53 Containing Administrative Changes Re Power Rerate Program ML20249C5121998-06-19019 June 1998 Proposed Tech Specs Pages Re Rev 2 to 960726 LAR to License DPR-22,to Establish TS Requirements That Are Consistent W/Analysis Inputs Used for Evaluation of Radiological Consequences of MSLB Accident ML20247K6341998-05-12012 May 1998 Proposed Reprinted Tech Specs Bases Pages,Containing Spelling & Grammatical Corrections ML20216D0021998-03-19019 March 1998 Proposed Tech Specs,Providing Consistent Wording Throughout TS & Providing Sound Basis for Frequency of Actions Required Each Shift ML20248L2001998-03-13013 March 1998 Proposed Tech Specs Revising SLMCPR B210059, Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents1998-03-0909 March 1998 Rev 1 to GE-NE-B2100594-1, Radiological Analyses of Design Basis Accidents ML20248L4101998-03-0606 March 1998 Revised Page 39 to Proposed TS Change ML20202H7061997-12-0404 December 1997 Proposed Tech Specs Increasing Plant Max Power Level from 1670 Mwt to 1775 Mwt ML20203A9771997-11-25025 November 1997 Proposed Tech Specs Re Condensate Storage Tank Low Level Hpci/Rcic Suction Transfer ML20199H5281997-11-0606 November 1997 Software Requirement Specification (SRS) ERDS-SRS-1-3, Process Computer Sys - Emergency Response Data Sys (ERDS) - Data Point Library ML20211J9801997-09-29029 September 1997 Proposed Tech Specs Page 249b & Cleaned Typed Page 249b, Adding Footnote to Topical Rept NEDE-24011-P-A Stating That Topical Rept Is Approved for Cycle 18 Only ML20210Q2971997-08-21021 August 1997 Proposed Tech Specs Re Safety Limit Min Critical Power Ratio ML20141B9181997-06-19019 June 1997 Proposed Tech Specs Re Update of Design Basis Accident Containment Temp & Pressure Response ML20137W2201997-04-11011 April 1997 Proposed Tech Specs 3.6.C Re Coolant Chemistry & TS 3/4.17B Re Control Room Emergency Filtration Sys ML20137B5081997-03-12012 March 1997 Rev 2 to Inservice Insp Exam Plan ML20149M7281997-01-23023 January 1997 Proposed Tech Specs 3.5/4.5.C of TS Bases Describing Min RHR & RHRSW Pump Requirements for Post Accident Containment Heat Removal & Submit Update to Design Basis Accident Containment Temp & Pressure Response ML20132C6531996-11-25025 November 1996 Proposed Tech Specs,Sections 2.1.A Re SLMCPR & 3.11.C Re Olmcpr.Changes Revise SLMCPR Values & Deletes Sentence Re OLMCPR Limit Penalty for Single Recirculation Loop Operation ML20117A1551996-08-15015 August 1996 Proposed Tech Specs Re Revision to TS Administrative Controls Section 6.1.F.1 Stating That Either 8 or 12 H Shifts Will Be Considered Normal & 40 H Will Be Considered Nominal ML20116G8951996-07-26026 July 1996 Proposed Tech Specs Increasing Max Power Level by 6.3% to 1,775 from 1,670 Mwt.Summary of Plant Mods for Power Rerate Implementation & Power Rerate Environ Evaluation Encl ML20116D8361996-07-26026 July 1996 Proposed TS Sections 3.6.C & 3/4.17.B Re Reactor Coolant Equivalent Radioiodine Concentration & CR Habitability ML20115D8621996-06-28028 June 1996 Rev 3 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20100Q3861996-03-0101 March 1996 Proposed Tech Specs Re Periodic Replacement of Containment Purge & Vent Valve Seat Seal ML20095J4341995-12-20020 December 1995 Proposed Tech Specs Re Main Steam Isolation & App J Leak Rate Test Requirements ML20095E7121995-12-11011 December 1995 Proposed Tech Specs,Removing TS SR 4.7.D.4 & Replaces Seat Seals for Drywell & Suppression Chamber Purge & Vent Valves Every Five Yrs ML20094M1981995-11-14014 November 1995 Proposed Tech Specs,Incorporating Requirements of Option B, Section Iii.A for Type a Testing (Primary Containment ILRT) ML20100M4821995-08-29029 August 1995 Revised Sections to Odcm,Including Rev 1 to ODCM-03.01,Rev 1 to ODCM-12.05 & Rev 1 to ODCM-13.05.5 ML20091K6821995-08-18018 August 1995 Proposed Tech Specs Section 3.7/4.7 SGTS ML20087J4251995-08-15015 August 1995 Proposed Tech Specs,Revising Max Individual MSIV Leak Rate Acceptance Criteria of 11.5 Scfh to Overall Criteria That Encompasses Four Main Steam Lines Into One Limit of 46 Scfh ML20086D8011995-07-0505 July 1995 Proposed Tech Specs Extending Surveillance Test Intervals & Allowable out-of-svc Times for Selected Instrumentation ML20085N0991995-06-22022 June 1995 Proposed Tech Specs Supporting Implementation of BWR Thermal Hydraulic Stability Solution ML20083Q8411995-05-18018 May 1995 Rewrite of Rev 2 to Engineering Work Instruction (Ewi) EWI-09.04.01, Inservice Testing Program ML20082N8711995-04-20020 April 1995 Proposed Tech Specs Re SBGTS & Secondary Containment ML20077S4551995-01-0909 January 1995 Startup Physics Testing Rept,Cycle 17 ML20069J1061994-06-0808 June 1994 Proposed TS Re SGTS & Secondary Containment ML20072P8011994-05-17017 May 1994 Rev 8 to Process Control Program, Installed Atcor Solidification Sys ML20065B6691994-03-28028 March 1994 Proposed Tech Specs Re Approved Analytical Methods for Developing Core Operating Limits Rept ML20065B6991994-03-28028 March 1994 Proposed Tech Specs Re Standby Gas Treatment Sys Initiation Instumentation ML20072P8101994-02-22022 February 1994 Offsite Dose Calculation Manual, Rev 0 ML20063C9941994-01-26026 January 1994 Proposed Tech Specs,Requiring Valves to Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA ML20062N8731994-01-0404 January 1994 Proposed Tech Specs 3.11, Reactor Fuel Assemblies & Bases Re Methodology for MCPR ML20059E6041994-01-0303 January 1994 Proposed Tech Specs,Revising Surveillance Requirement 4.6.E.1.a to Require Valves to Be Tested Per Section XI Inservice Testing Requirements of ASME Boiler & Pressure Vessel Code ML1132102881993-11-30030 November 1993 Proposed Tech Specs Re Removal of Chlorine Detection Requirements & Changes to Control Room Ventilation Sys Requirements 1999-09-30
[Table view] |
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Exhibit B l Monticello Nuclear Generating Plant License Amendment Reauest Dated November 14.1995 l J
Technical Specification Pages Marked Up l with Proposed Wording Changes 1
Exhibit B consists of the existing Technical Specification pages marked up with the proposed changes. Existing pages affected by this change are listed below-P_R92 159 160 184 185 (new) l
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9511210316 951114 PDR ADOCK 05000263 P PDR
Perform required visual examinations and leakage rate ~7 '.
y --
t: sting for Type A containment integrated leakage rat 3 C ombel mAxe mu m -Noe [%Th Mage tests in accordance with Regulatory Guide 1.163, and Type . ,
,B and C tests in accordance with 10 CFR 50, Appendix J, ,
._. ._ j
- Option A, as modified by approved exemptions.
- n -
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS J
' ~
pr ma s
- b. When Primary Containment Integrity is required, b con all b demon rated -
nm th; f" p-in-a acwe ue. d leakage rates shall be limited to: d ch d 5: f:dni .:d
- 1. An overall integrated leakage rate of less
% e se- edul
+ir : 1:r . : rit5 4.0 cri ria, a nods g
[
7 than or equal to La, 1.2 percent by weight anodprovi ema w T ou M onsofjf0CFRP t 50; flon g' of the containme_nt air _per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa. }y orp9 rove e.f.e tw .
42 psig. $ggQ q j-(,g- -
{
1.
Q4 ege A - -
T ee Type A overall integrate A combined eakage rate of less than or equal cont ent leakage rate t shall
- 2. h intervals
- to 0.6La for all penettations and valves, be conduc at 40i10 ne pt f:r ::1 : ::: 1 :12tir- relr::, during shutdo a _ a during each subject to Type B and C tests when pressurized 10-year servi od. The third test of e set shal conducted to Pa 3L{2. p sig. duri e shutdown for ti 0-year 4L
- 3. Less than or equal to 41 scf per hour or all t inservice inspection.
eny :ne main steam isolation valveSwhen tested Dele.Tarl at 25 ps 2. any periodic Type A test fails
@ meet subseque 75La, the test schedul pe A tests sh be or With the measured over integrated primary roved the Commission.
containment leakage ce exceeding 0.75La, or the reviewed an measured combined 1 kage rate for all penetrations If two consecuti e A tests fail to and valves, _-i- rte-- irelatie- rel _-- ;, meet 0.75La, a e t shall be eeept[n_dCtestingexceed ype B La, or performed a east every onths until leak rate exceeding t c5- f per hour I two con utive Type A tests m 0.75La, the measgr time the above test sche le for an,8_n: main steam isolation valven restore at w leakage rates to less than or equal to these values be resuged.
prior to increasing reactor coolant system temper- e\ste, d ature above 212*F or, alternatively, restore 3. e A test leakage rates s measured leakage rates to within these limits within calculat observ a converted one hour or be in at least Hot Shutdown within the to absolute va . analyses next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the shall ormed to select ced following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. integrated leakage measuremen m.
e "
- ie test of the see ar i Coyd*gned vvwMmtAm Du3 o servlCe periot onducted during i th e ueling outage. ,
159 3.7/4.7 ' "" l '"' : 1/:'/3
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SkIRVEI CE REQUIREMENTS C5 elate
- 4. e accuracy of each Type A test shall b '
ve ied by a supplemental test which:
- a. Con a the accuracy of the at by
. verify that the differen between the supp ental data and e Type A !
test data within 0.2 , and i
- b. Has duration su e nt to establish accurately the ch e in leakage rate between the Typ At and the supple- ,
mental test, d I
- c. Requires e rate of gas in ted into t containment or bled the cont nment during the supplemen to be limited between 75 to 1 te b e\<t
- 5. Q: 5 ::' t_;t: ;5:11 5 5.p_t;d
.. ,e.. . . . _ _ . . . . . . . . . ,
_L. . A _ r__ c__m_.. ___m_m____, _a e s. __
mt_s
!".._ ,Z: 1 Y :::;_~~,2::Ti.i:_ _ _ . _ - . . - - . . . .,2 22 _ .' _Z. . ." - " ' '
- lin "::leti:n ::1 ::._.-- in steam ,
- isolation va e tests shall conducted i with gas at > psig east _S :: th:. A
___t __2 i__r___ ..__,In 1, _ _t _ i i i
21- :Z!__:1_ 3 rX : s 7_- _ _ m _ _ m , _____2
..:i..:'--"::::: ,2 '.3C C"'Z'TII:"!_ s! /
._.- _ : ~. ; 7
~.li c_ :'.--#--
__. . ---- :. 2 EE.li _r-:
. -tosse. leak i rate o 11. ", yauf per hour sh b emonstrated +eek. main i steam ne' solation valves, a.ll !
r S. _k 5 I ._m ft , - ~ 7 J. .
3.//4.7 160
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_om ,,o ,,,.,.o i as s .a - my a wg w - [
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j Bases Continued: . .
l
! While the design of the Monticello plant predates 10 CFR Part 50, Appendix J, " Primary Reactor Containment Lankage Testing for Water-Cooled Power Reactors," testing substantially conforms to the
- requirements of Appendix J. The design of the plant was thoroughly reviewed to determine where compliance with Appendix J was, impossible or impractical. In each case where a departure from the requirements of Appendix J was identified, a request for exemption from the requirements of Appendix J or a plant modification was proposed and submitted for NRC Staff review. Exemptions were proposed in those cases where compliance with Appendix J would have provided no meaningful improvement in plant safety.
In their review of Appendix J compliance II) , the NRC Staff approved a number of exemption requests, denied others, and provided'necessary interpretation and clarification of the requirements of i Appendix J. The Technical S$ecification surveillance requirements reflect the results of this review.
Exemption from the requirements of Appendix J was provided in the following areas:
- a. Testing of valves sealed by water
- b. Low pressure testing of main steam line isolation valves
- c. Low pressure testing of the primary containment airlock
- d. Reduced airlock testing frequency when the airlock is in frequent use s/
The Monticello airlock is tested by pressurizing the space between the inner.and outer doors.
Individual door seal leakage tests cannot be performed. Since the inner door is designed to seat with containment pressure forcing. the door closed, special bracing must be installed for each leakage test. The outer door must be opened to install and remove this bracing. Because of the l complexity of this operation,~up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be necessary to perform a leakage test.
(1) Letter from D G Eisenhut, Director, Division of Licensing, USNRC, dated June 3,1984, " Safety .
Evaluation by the Office of NRR, Appendix J Review". !
4.7 BASES - - . TA;; IS ra0E 100 184 :
REV .., i .f ,f . , ,
_ _ - _ _ _ _ . _-_ - _ - - _ _ - _ - _ _ _ _ . _ _ _ _J
/ .
x X
Bases Continued:
On September 26, 1995, Regulatory Guide 1.163 became effective providing guidance on performance based testing to the requirements of 10 CFR 50, Appendix J, Option B. Monticello has adopted Option B, Section ,
III.A of 10 CFR Part 50, Appendix J, . for_ Type A primary reactor containment integrated leakage rate - l testing. Monticello will continue to perform Type B and C testing in accordance with 10 CFR Part 50, ,
I Appendix J, Option A. r 4
1 j 'I I
I i
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l 4.7 BASES NEXT PAGE IS PAGE 188 185
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Exhibit C Monticello Nuclear Generating Plant License Amendment Reauest Dated November 14.1995 Revised Monticello Technical Specification Pages Exhibit C consists of revised Technical Specification pages that incorporate the proposed changes. The pages included in this exhibit are as listed below. Note that due to removal of specific material and the resulting reconciliation, page 161 is no ;
longer included.
.Pjagg 159 160 184 185 (new) i 1
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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS
- b. When Primary Containment Integrity is required, b. Perform required. visual examinations and leakage rates shall be limited to: leakage rate testing for Type A containment '
integrated leakage rate tests in accordance
- l. An overall integrated leakage rate of less with Regulatory Guide 1.163, and for Type B and than or equal to La, 1.2 percent by weight C tests in accordance with 10 CFR 50, Appendix of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pa, J, Option A, as modified by approved 42 psig. exemptions.
i .2. A combined maximum flow path leakage rate 1. Deleted of less than or equal to 0.6La for all penetrations and valves, subject to Type B 2. Deleted and C tests when pressurized to Pa, 42
, psig. 3. Deleted
- 3. Less than or equal to 46 scf per hour 4. Deleted combined maximum flow path leakage for all main steam isolation valves when tested at 5. Deleted 25 psig.
With the measured overall integrated primary i containment leakage rate exceeding 0.75La, or the measured combined leakage rate for all penetrations and valves subject to Type B and C testing exceeding 0.6La, or the measured combined maximum flow path leakage rate exceeding 46 scf per hour for all main steam isolation valves, restore leakage rates to less than or equal to these values prior to ,
increasing reactor coolant system temperature above 212*F or, alternatively, restore measure .
leakage rates to within these limits within one hour or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i 159 3.7/4.7
- _ _ _ _ _ + , --.,_--_--._-~_e-v_m -r. . , = ,- .- a-~m , -m. < , . ~ , v - _ - - - - - _ - _ - - - - _ - _ - - _ , - - - - - . _ _ . _ _ . _ - - - _ _ - . - _ - - - _ _ _ _ _ ~ _
3.0 LIMITING CONDITIONS EDR OPERATION 4.0 SURVEILIANCE REQUIREMENTS
- c. When Primary Containment Integrity is required, c. The primary containment airlock shall be the primary containment airlock shall be demonstrated operable:
operable with:
- 1. By performing overall airlock leakage rate
- 1. Both doors closed except when the airlock testing in accordance with 10 CFR 50, is being used, then at least one airlock Appendix J, as modified by approved door shall be closed, and exemptions.
- 2. An overall airlock leakage rate of less 2. Deleted than or equal to 0.05La at Pa or 0.007La at 10 psig. 3. At six month intervals by verifying that only one door can be opened at With the primary containment airlock a time. If the airlock has not been inoperable, maintain at least one airlock door used since the last door interlock closed and restore the airlock to Operable test, this test is not required.
status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold d. The interior surfaces of the drywell shall Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. be visually inspected each operating cycle for evidence of deterioration.
3.7/4.7 160 NEXT PAGE IS PAGE 163
o . . _ _
t i
,~f Bases Continued:
l While the design of the Monticello plant predates 10 CFR Part 50, Appendix J, " Primary Reactor. ,
i Containment Leakage Testing for Water-Cooled Power Reactors," testing substantially conforms to the f requirements of Appendix J. The design of the plant was thoroughly reviewed to determine where !
compliance with Appendix J was impossible or impractical. In each case where a departure from the requirements of Appendix J was identified, a request for exemption from the requirements of Appendix l J or a plant modification was proposed and submitted for NRC Staff review. Exemptions were proposed in those cases where compliance with Appendix J would have provided no meaningful improvement in j plant safety. t i
! In their review of Appendix J compliancetu, the NRC Staff approved a number of exemption requests, I i denied others, and provided necessary interpretation and clarification of the requirements of Appendix J. The Technical Specification surveillance requirements reflect the results of this ;
review.
Exemption from the requirements of Appendix J was provided in the following areas:
- a. Testing of valves sealed by water 5
- b. Low pressure testing of main steam line isolation valves.
- c. Low pressure testing of the primary containment airlock
- d. Reduced airlock testing frequency when the airlock is in frequent use The Monticello airlock is tested by pressurizing the space between the inner and outer doors.
i Individual door seal leakage tests cannot be performed. Since the inner door is designed to seat !
with containment pressure forcing the door closed, special' bracing must be installed for each leakage test. The outer door must be opened to install and remove this bracing. Because of the ,
complexity of this operation, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> may be necessary to perform a leakage test. i i
(1) Letter from D C Eisenhut, Director, Division of Licensing, USNRC, dated June 3,1984, " Safety Evaluation by the Office of NRR, Appendix J Review".
4.7 BASES 184 g j REV I i
i
s Beses Continued: ,
On September 26, 1995, Regulatory Guide 1.163 became effective providing guidance on performance based testing to the requirements of 10 CFR 50, Appendix J, Option B. Monticello has adopted Option B,Section III. A of 10 CFR Part 50, Appendix J, for Type A primary reactor containment integrated leakage rate testing. Monticello will continue to perform Type B and C testing in accordance with 10 CER Part 50, Appendix J Option A.
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