|
---|
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
'
s s l O O l l . .
Ulatoly, l)ocMI,3a l
l EXHIBIT B
, , LICENSE AMENIHENT REQUEST DATED DECDiBER 1,1975
' Exhibit B, attached, consists of newly prepared pages for the Appendix A
.., Technical Specifications as listed below. These pages incorporate the v . ",q':)( proposed changes.
- d:
ay. g ,; ,
PAGES 50 66 1 1890
,* 189F l
l' i
l t
t l
I l
e l
'I 1
1 i
il 9102000374 751201 3 PDR ADOCK 0500 P
-- _ _ __ . _ _ _ . - _ _ - - __ _ _. _ _. u _ . _ _
>g_
~
Thble 3 2.1 J- ,
Instrumentation '! hat Initiates Primary Contaitunent Isolation Functions , . ,
i Min. No. of Operable -
Total No. of Instnt- or Operating Instru-ment Channels Per ment Qiannels Per Trip Bequired Function Trip Settings _ Trip System System (1,2) Coralitions*
- 1. Main Steam and Becire Semqple Lithes (Group 1)
- a. Iow Iow Heactor d6'-u n.10" 2 2 A O
! Weter Ievel
- b. High Flow in Main
{ Steen Line il' 0%
4 rated 8 8 A
- c. High tesp. in k in 2 of k in each i Steam Line Tunnel b200% 8 of 2 sets A
- d. Iow Pressure in hin I Steam Line (3) d825 pais 2 2 3
- e. R16h Radiation In Main 610 I Nonnel Steam Line Tunnel backgroual at 2 2 ,
A rested power
- 2. RER System, Head Cooling, Dryvell, Stasp, TIP (Group -
2)
- e. Iow Beactor Water 310'6" above the 2 2 C Ievel tcp of the active fuel 3 2/k.2 50 I
i "We, m _
l
+
.s. ,
e Bases Continued:
32 instrumentation is provided which causes a trip of Group 1 isolation valves, he primary function of the instrumentation is to detect a break in the main steenline, tnus only Group 1 valves are clored. For the worst case accident, main steamline break outside the dryvell, this trip setting of 1h0% of rated steam flow in conjunction with the flev limiters and main stearline valve closure, limit the mess inventory loss such tha< fuel is not uncovered, fuel clei temperatures remain less than 1000 F and release of radioactiv! ty to the environs is well belov 10 CFR 100 guidelines.
Reference Sections 14.6.5 FEAR.
Temperature monitoring instrumentation is provided in the nain steemline tunnel to detect leeks g in this area. Trips are provided on ghis inst 2.nentation end when excee'ied cause closure of Group 1 isolation valves. Its setting of 200 F is lov enough to detect leaks of the order of 5 to 10 gpm; thus, it is capable of covering the entire spectn:m of breaks. For large breaks, it is a back-up to high steam flow instrumentation discussed above, and for small % reeks with the resultant small release of radioactivity, gives isolation before the guidelinen of 10 CFR 100 are exce-ded.
High radiation monitors in the main steamline tunnel have been provided to detect gross fuel failure I
resulting frce a control rod drop accident. This instnzmentation causes closure of Group 1 valves, I the only valves required to close for this accident. With the established setting of 10 times nomal background, and mein steamline isolation valve closure, firsion product release is limited so that 10 CFR 100 guidelines are not exceeded for this accident. Reference Section 14.6.2 FSAR.
De perfomance of the process radiation monitoring system relative to detecting fuel leakage shall be evaluated during the first five years of operation. The conclusions of this evaluation vill be reported to the Atomic Energy Ccruission.
Pressure instnzmentation is provided which trip- when main steamline pressure drops belov 825 l
peig. A trip of this instrumentation results in closure of Group 1 isolation valves. In the g
" refuel" and "Startup" mode this trip function is bypassed. This 11tnction is provided primarily to provide protection against a pressure regulator malfunction which would cause the control and/or l bypass valves to open. With the trip set at 825 psig inventory loss is limited so that fuel is I
not uncovered and peak clad te=peratures are much less then 1500 F; thus, there are no fission products available for release other than those in the reactor water. Reference License Amendment Request Dated December 1,1975 from L. O. Mayer (NSP) to R S. Boyd (USNRC).
66 REV 3.2 BASES .
M
- - -~ - J. ----- - --
..ri
') *
, _ : 3
-J
~'
3.0 LIMITING CmDITIWS F,0R _0PERATIW 4.0 SURVEILLANCE REQUIREMDITS
~
C. Minf== Critical Power Ratio (MCPR) C. Minimum Critical Power Ratio OtCFR)
During steady state power operation, 1. MCPR shall be checked daily the Operating MCPR Limit shs11 be during reactor power operation at l 21.38 for 8x8 fuel and 21.29 for E 257. rated thermal powsr. -
7x7 fuel at rated power and flow.
For core flows other than rated the 2. Whenever the plant technical staff determines Operating PCPR Limit shall be the that more frequent surveillance of MCPR is above value nazitiplied by Kg , neces % ;, it shall specify an augmented where Kg is given by Figure 3.11.2. :;.,rvet11ance program comunensurate with reactor If at any time it is determined that conditions, the limiting value of NCPR is being exceeded, action shall be taken imunediately to restore operation to within prescribed limits.
9 189D 3.11/4.11 REV a < w. , ,
- ~----.:- -~ - - . ..-- . - 2. - _ -- - ~. - - e =-
l ,
. I a .
e Bases 3.11- (continued) ," ",
C Minietzn Critical Power Ratio (MCPR)
The ECCS evaluation presented in Reference 4 assumed the steady state MCPR prior to the postulated loss of coolant accident to be 1.18 for all fuel types. The Operating MCPR Limit l of 1.33 for 8x8 feel and 1.29 for 7x7 fuel is detemined from the analysis of transients discussed in Bases Sections 2.1 and 2.3. By maintaining an operating MCPR above these limits.
the Safety Limit of 1.06 (T.S.2.1. A) applicable to all fuel types is pintained in the event of the most lim'_ ting abnomal operational transient.
For operation with less than rated core flow the Operating MCPR Limit is adjusted by multiplying the above limit by K f. Reference 5 discusses how the transient analysis done at rated conditions encompasses the reduced flow situa' tion when the proper gK factor g
is applied.
It is recognized that MCPR is a calculated parameter that is not continually monitored and alanned directly during core power distribution and thermal-hydraulic changes. If at the time of the evaluation it is found that the limits are being exceeded, there is always an action which will return the MCPR to within prescribed limits, namely power reduction. Under most circumstances, this will not be the only alternative. Whenever the limit is exceeded the monitored value will be documented and available for review, audit and inspectf on of plant operations.
The only way to violate the Limiting Condition for Operation is to knowingly allow operation beyond the prescribed limits without taking the necessary action to restore the MCPR to within prescribed limite.
Re ferences
- 1. " Fuel Densification Effecte in General Electric Boiling Water Reactor Fuel," Supplements 6, 7, and 8, NEDM-10735, Augusq 1973.
- 2. Supplement I to Technical Report on Densification of General Electric Reactor Fuels, December 9 14, 1974 (USAEC Regulatory Staff)
- 3. Ccemunication: V A Moore to I S Mitchell, " Modified GE Model for Fuel Densification,"
Docket 50-321, March 27,1974.
- 4. "Monticello Nuclear Generating Plant Loss-Of-Coolant Accident Analysis Conformance with 10 CFR 50 Appendix K, August 1974," L 0 Mayer (NSP) to J F O' Leary, August 20, 1974.
- 5. " General Electric BWR Generic Reload Application for 8 x 8 Fuel," NEDO-20360. Revision 1, Novembe r, 1974 3.11 BASES F n.
NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL
, * (TEMPORARY FORM)
CONTROL NO: 13535 e
, FILE:
FROM: Northern States Power Cc . DATE OF DOC DATE REC'D LTR TWX RPT OTHER 55401 i
g e g s, Minn. 12-1-75 12-3-75 XX
-- TO: . ORIG CC OTHER SENT NRC POR XX Mr. R.S. Boyd 1 signed XX 39 SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXX 40 50-263 -
DESCRIPTION: Ltr trans the following: ENCLOSURES: Request for Amdt to OL/DPR-22 notarized 12-1-75 / Tech Specs with Exhibit A entitled " Proposed Changes to Tech Specs App. A of OL/DPR-22'? & ExhibitB entitled
" License Amdt Request dated Dec. 1.,1975"...
(3 Orig & 37 CC' rec'd)
PLANT NAME: Monticello Plant FOR ACTION /INFL RMATION DHL 12-3-73 BUTLER (L) SCHWENCER (L) dlEA NN (L) REG AN (E) REID(L)
W/ Copies W/ Copies W opies W/ Copies W/ COPIES CLARK (L) STOLZ (L) DICKER (E) LEAR (L)
W/ Copics W/ Copies W/ Copics W/ Conics i PARR (L) VASSALLO (L) KNIGHTON (E) Spins W/ Copies W/ Copies -
W/ Copies . W/ pies KNIEL (L) PURPLE (L) YOUNGBLOOD (E) M. Plt KLeV-i W/ Copics W! Copies W/ Copies W/ opies INTERNAL DISTRIBUTION istm 5 m TECH REVIEW DENTON LIC ASST A/T IND .
FNHLFDR SCHRdl5 DER GRIMES OGC, ROOM P 50GA 68. DIGGS (L) B R AITM AN MACCARY GAMMILL H. GE ARIN (L) SALTZMAN GOSSICK/ST AF F fNIGHT KASTNE R CASE E. GOULBOURNE (L) MELTZ WAWLICKl. BALLARD P. KREUTZER (El GIAMBUSSO SHAO SPANG LE R PLANS BOYD J. LEE (L)
STELLO MCDONALD MOORE (L) HOUSTON M. RUI.lER00?(L)
ENVIRO S. REED (E) CHAPMAN DEYOUNG (L) NOVAK MULLEli M. SERVICE (L)
SKOVHOLT (L) ROSS DUBE (Ltr)
DICKER S. SHEPPARD (L) E. COUPE GO8.LER (L) (Ltr) IPPOLITO KNIGHTON M. SLATER (E) PETERSON P. COLLINS TEDESCO YOUNGBLOOD H. SMITH (L)
DENISE HARTFIELD (2)
J. COLLINS REGAN S. TEETS (L) KLECKER W.G OPR -
LAIN AS *@ CT LDR G. WILLI AMS (E) EISENHUT
- 1LE & REGION (2) BENAROYA EM WIGGINTON MIPC V. WILSON (L)
VOLLMER _.I A@.ES _
R. INGR ' M (L)
. M. DUFCAN(a EXTEdNAL DISTRIBUTION -
- LOCAL PDR_ Minneapolis , Minn.
-TIC (ABERNATHY) (1)(2)(10) - N ATION AL LABS 1 - PDR. SAN /LA/NY q
- NSIC (BUCHANAN) 1 - W. PENNINGTON, Rm E 201 GT 1.- BROOKH AVEN NAT LAB 1 - ASLB -
i - CONSULTANTS 1 - G. ULRIKSON ORNL Newton Anderson NEWM AR K/B LUME/AG B ABI AN ACRS : ' _ < m G/S E NT 7*O /. jf.
4 -