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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] |
Text
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3.0 LIMITING CONDITIONS FOR OPEPATION 4.0 SURVEILIANCE REQUIPDENTS
- 3. Ibe diffuser to lower plenum differential pressure reading on an individual jet ptry is 107. or more, less than the mean of all jet pung differential pressures.
H. Hydraulic Snubbers H. Hydraulic Snubbers .
- 1. During all modes of operation, except Cold Shut- The following surveillsace requirements apply to all down and Refueling Shutdown, all hydraulic hydraulic snubbers listed in Table 3.6.1:
snubbers listed in Table 3.6.' shall be operable except as noted in 3.6.H.2 through 3.6.H.4 1. All hydraulic snubbers whose seal material has been below. demonstrated by operating experience, lab testing, or analysis to be compatible with the operating
- 2. From and after the time that a hydraulic simbber environment shall be visually inspected. *lhis is determined to be inoperable, continued reactor inspection shall include, but not necessarily be operation is permissible only during tne succeed- 3g g g 7 TT4 ing 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless the snubber is sooner made reservoir, fluid connections, and linkage connec-c-
g PeraMe. tions to the piping and anchor to verify snubber Perubility in accordance with the following 75 3. If the requirements of 3.6.H.1 and 3.6.H.2 cannot schedule-
@O be met, an orderly shutdown shall be initiated om and the reactor shall be in a cold shutdown No. of Snubbers Found Next Required Inspectior M condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Inoperable During Inspec- Interval o9
' ' " " to be inoperable while the reactor
" ' " ' ' '" ' '~' ' " ' """' '" " " "
3 f*$
fu -
"is determined is in the chutdown or refueling mode, the snubber Interval O 18 months + 25%
g$ shall be made operable prior to reactor startup. 1 12 months {25%
2 6 months + 25%
3,4 12A days T 25%
5,6,7 62 days i 25%
>S 31 days 1 25%
121 306/4.6 ag
3.0 I.IMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQl1IREMENTS Snubbers may be added to safety related The required inspection interval shall not be
- 5. lengtbened more than one step at a time.
systems without prior License Amendment to Table 3.6.1 provided that safety evaluations, documantation and reporting Snubbers rny be categorized in two groups, are provided in accordance with 10CFR " accessible" or " inaccessible" based on their 50.59 and that a revision to Table 3.6.1 accessibility for inspection during reactor is included with a subsequent License operstion. These two groups my be inspectc.d Amendment request. independently accordin6 to the above schedule.
- 2. All bydraulic snubbers whose seal mterials are other than ethylene propylene or other material that has been demonstrated to be compatible with the operating environment shall be visually in-l spected for operability every 31 days.
3- deleted
- ! 4. Once each refueling cycle, a representative sample of 10 snubbers or approxistely 10% of the snubbers, whichever is less, shall be functionally tested for operability including verification of proper piston mvement, lock up, and bleed. For each unit and subsequent unit found inoperable, an additional 10%
or ten onubbers shall be so tested until no more failures are found or all units have been tested.
Snubbers designated in Table 3 6.1 as being especially difficult to remove or located in High Radiation Areas are exermt from this requirement.
5 Snubbers may be reclassified as being in or out uf High Radiation Areas in Table 3.6.1 based on the most recent radiation survey provided that a revision 3.6/4.6 to Table 3 6.1 is included with a subtequent License Amendment Fequest. g REV
i i
t l
TABLE 3.6.1 e BE1 RSof 2)
! SAFETY RELATED HVDRAULI 5 , [
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7 I Sa:UB8E R NO . SYSTEM LJCATIDN E L EV AT ION AllMUTH HIGH R ADI A- D t'F ICUL T ACCESSISLE -A tAIRLDCR 0 REFS TION AREA 10 REMOVE INAECESSISLE-t [
j - --____________
g PS1-H2 MAIN STE AM DRYWELL 9 53 071 i
[
l P51-H3 MAIN 5 TEAM CRYWELL 960 148 I PS 2-H2 MAIN STEAM DRYW E LL 950 123 i PS3-H2 MAIN ST E AM DRYWELL 9 50 240 t i
P54-H3 MAIN STEAM DRYWELL 950 212 3 DRYWELL 9 50 110 t l Rv24-H3 S AF E T Y-R EL I EF I
Rv24-H4 S AF ET Y-R ELIEF DR1 DELL 9 15 100 Rv24-H4A S AFE T Y-R Et t EF DRYWELL 9 35 100 t Rv24-H5 5AFETY-RELIEF DAY WE LL 9 35 110 t DAYWELL 947 048 x 1 AV24A-H4A S AFE TY-R ELI EF RV24A-NF SAFETY-RELIEF DRYWELL 9 53 115 i 9 39 032 1 !"
RV24A-H8 S AFET Y-R EL IE F DRYWELL i Rv25-M1 S AFE TY-R ELI EF DRYWELL 953 180 g DRYWELL 953 180 x t 4
Rv25-H1A S AFET Y-R EL IE F 190 K 4
Rv25-H2 S AFE T Y-R EL I E F DRYWELL 948 t ,
DRYWELL 948 193 x I l RW25-H2A SAFETY-REttEF x l Ev25-H3 SAFET Y-R ELI EF DRYWELL 9 34 180 ORYWELL 945 120 x x [
4 Rv25A-H2 SAFETY-RELIEF x x j Rv 25 A-H2 A SAFETY-RELIEF DRYWELL 945 120 1
! t
- RV25A-H7 S AFE T Y-R EL I E F DRYWELL 953 135 I SAFETY-RELIEF DRYWELL 953 200 x [
l CW 26-H 1 '
RW26-H1A S AF E T V-R EL I EF DRYWELL 953 200 t x
! SAFETY-RELIEF DRYWELL 9 47 200 Rv 26-H 2 I r SAFETY-RELIEF -DRYWELL 947 200 KV26-H2A '250 t RV264-H2 S AFE T Y-R EL I E F DRYWELL 940
' ORYWELL 935 250 I CV26A-H2A S AFET Y-R EL I EF 320 t RY27-M1 S AFETY-RELI EF DRYWELL 9$0 [
DRYWELL 9 94 230 t RW2F-HIA S AFE T Y-R EL ICF t
$AFETY-RELIEF DRYWELL 945 2F0 RV27-45 945 270 t
[
j_ RV27-H4 S AF E T Y-R EL I EF DRYWELL 953 290 t ,
RV274-H2 A S AFET Y-R ELIEF DRYWELL
]
9 53 290 t f
! Rv27A-H3 S AFE TY-R ELIEF DRYWELL l SAFETY-RELIEF DRVWELL 9 38 293 I CW27A-H9 279 x I !
55-1 MAIN STEAM DRYWELL 953 I'
922 315 K x I l 55-1AR RECIR CUL AT IENs DRYWELL l 9 ** 135 x x 1 j 55-104 RECIRCUL AT IDN DRYWELL I DAYWELL 952. 302 I
] 55-11 F EEDW AYER 9 52 058 : ;
i 55-12 FEEDW ATER ORYWELL 952 258 I ;
j 55-13 F EE DW ATE R DRYWELL 952 096 I ,
- 55-14 FEEDWATER DRYWELL 4M 0F2 x t I
$5-17A RHR ORYWEtt i DRYWELL 9M 072 x 1 '
55-178 RHR 9M 288 1
! $5-18A RHR DRYWELL DRYWELL 9M 288 I
} 55-188 RHR 9 64 341 1 55-19 R HR ORYWELL r !
DRYWELL 9 53 081 x 'I I 55-2 MAIN STE AM x x I 55-2AR RECIRCULATIDM DRYWELL 927 30 2 i !
1 121B 3.6/4.6
- REV j
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l
_ _ _ _ _ __ _- ~ _ _ __ _ _ _ - -_ _ ____ _ _ _ - . _ _ .. . _ . _ . _ _ _ _ _ _ _ _ . _ _ _ _ ____ _- . -
TA BL E 3.6.1 ( Bage 2 of 2 )
SAFE TY MELATED HYDR AULI C SNUB 8ERS
~~ ~~~~~~~
SNUe8ER NO. SYST LM LOCallON EL EV AT ION AZIMUTH HIGHkADIA DIhAICULT ACCESSIRLE .A (AIRLOCR 0 REF6 flog AREA T3 REMOYE IN aC CE S SI SL E -I 92T 122 x 1 55-2BR R EC1 R CUL Af l 0N DR YW E L L x t 55-20 R HR CRYWELL 9 64 019 55-3 Ma t'4 STEAM ORYWELL 9 50 212 1 DRYWELL 92T 728 z I 55-3AR R ECIRCUL ATIDW x g 55-38R R ECIRCUL ATI ON DR YW E L L 92T 148 MAIN STEAM DRYWELL 950 148 1 35-4 I 55-4 AR I A) RECIRCUL Afl0N ORYWELL 9 34 302 9 14 323 I 55-4AR481 RECIR CUL ATION DRYWELL RECIRCULATION ORYWELL 9 34 120 1 55-48RIA8 149 I 55-48Rt03 R ECIR Cut a it 0N DRYWELL 9 34
~
t 55-40 HPCI MAIN STEAM C HASE 141 315 x I 55-5AR R ECIR CUL AT I ON ORYWELL DR YW E L L 941 135 x g 55-584 RECIR CUL AT I ON DRYWELL 953 261 x 1 33-6AR R EC I R CUL Af l 0N 099 x 55-68R RECIRCUL ATION DRYWELL 9 53 I DRYWELL 953 240 x 55-7 MAIN STE AM 323 1 55-7AR RECIR CUL AT ION CRYWELL 9 53 9 53 032 I 55-78R R ECIR CUL AT ION DRYWELL DAYWELL 953 120 x :
55-8 MAIN STEAN x I 55-8AR R ECIR CUL AT I ON DRYWELL 92T 270 DRYWELL 927 090 x I
$5-88R RECIR CUL AT I ON A 55-21 RHR TORUS FL L% - 5 WALL A 55-22 R HR TORUS FL Lv - 5 WALL A
'3 R HR 8 RHR ROON FL LV A
55-4+ R HR A RHR ROOM FL LV A
55-25 R HR TORUS CA ThR-5E WALL A 55-26 CORE SPRAY 8 RHR ROOM FL LVL A 55-27 CDRE SPR AY 8 RHR ROOM FL LVL A
$5-28A COME SPRAY A RHR ROOM FL LYL A 55-288 s0RE SPR AY A RHR ROOM FL LVL &
R HR OVER N2 AN ALYZER 9 $4 x 55-29 s A R HR OVER N2 AN8LYZER 9 54 55-30 A 55-31 R HR TORUS CAihK A 55-32A RHR A RHR ROOM - 8. HK 916 m A RHR ROGM - SV HR 916 x A 55-328 AHR A >
55-33 R HR ABOVE TORUS A 55-34 R HR ABOVE TORUS A 9 12 v 55-35 HPCI HPCI RCOM - N WALL A 55-36A HPC I HPCI RCOM - F L LWL A 55-368 HPCI HPCI ROOM - FL LVL y A HPCI HPCI ROOM -W Watt 9 05 55-37 9 06 . A 55-38A RCIC RCIC RCOM - W WALL m A RCIC RCIC RCOM - W WALL 9 06 55-388 92T A l 55-41 CORE SPR AY A8GWE TORUS CATWR A HPCI ABOVE TORLS RING HOR 9 06 55-42 121c 36/4.6 REV f
H. Hydraulic Snubbers (c ontd .)
Examination of defective snubbers at reactor facilities and material tests performed at several laboratories has shcun that millable gum polyurethane deteriorates rapidly under the temperature and moisture conditions present in many snubber locations. Although molded polyurethane exhibits greater resistance to these conditions, it also may be unsuitable for application in the higher temperature environments. Data are not currently available to precisely define an upper temperature limit for the molded polyurethane. Lab tests and in-plant experience indicate that seal materials are available, primarily ethylene propylene compounds, which should give satisfactory performance under the most severe conditiocs expected in reactor installations.
To further increase the assurance of snubber reliability, functional tests should be performed once each refueling cycle. These testr will include stroking of the snubbers to verify proper piston movement, lock-up and bleed. Ten percent or ten snubbers, whichever is less, represents an adequate sample for such tests.
Observed failures on these samples should require testing of additional units. Snubbers in High Radiation Areas or these especially difficult to remove need not be selected for functional tests provided operability was previously verified. Snubbers are considered especially difficult to remove if they (1) have a rated capacity greater than 50,000 lb, (2) are located greater than 5 feet above the adjacent platform, or (3) located greater than 3 feet below the adjacent platform.
3.6/4.6 BASES 138A Het
AMit$lON DOC K E T NyV D{ Q U S. NUCLt An et cVL ATODY '
NHC r onu 195 '
50-?63 o 788 '"""C'"
- NRC DISTRIDUTION ron PART 50 DOCKET MATCHI AL THOM: NORTHERN STATES POWER C,0. oaf t Or occuvtwt 10: V. STELLO MINNEAPOLIS, MINN. 10-1-76 _
L.O.MAYER oaf t atCeive o 10-4-76 .
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