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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999
Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs
ML20210M6171999-08-0404 August 1999
Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys
ML20210B5121999-07-15015 July 1999
Pbnp Simulator Four-Yr Rept
ML20209C1831999-07-0101 July 1999
Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS
ML20205R6741999-04-12012 April 1999
Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR
ML20203A2261999-02-0202 February 1999
Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design
ML20202F6521999-01-29029 January 1999
Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes
ML20154G5601998-10-0707 October 1998
Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility
ML20154H4231998-10-0505 October 1998
Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis
ML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20154C1941998-09-28028 September 1998
Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels
ML20153G7361998-09-23023 September 1998
Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers)
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20236W7861998-07-30030 July 1998
Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability
ML20249C3811998-06-22022 June 1998
Proposed Corrected Tech Specs Pages Re Radiological Effluents
ML20248C6651998-05-28028 May 1998
Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses
ML20248G1671998-05-27027 May 1998
Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1
ML20203K9571998-02-26026 February 1998
Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12
ML20203K2981997-12-15015 December 1997
Proposed Tech Specs Re Administrative Controls
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20247P2681997-09-23023 September 1997
Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles
ML20210M5151997-08-14014 August 1997
Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test
ML20210J0331997-08-0707 August 1997
Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording
ML20140C9111997-06-0303 June 1997
Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1
ML20141C5931997-05-0909 May 1997
Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140D7251997-04-14014 April 1997
Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c
ML20140D7091997-04-14014 April 1997
Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20137N6451997-04-0202 April 1997
Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20137C8331997-03-20020 March 1997
Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
1999-08-04
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20154C0561998-09-30030 September 1998
Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval
ML20206E2731998-08-26026 August 1998
Rev 11 to Pbnps Odcm
ML20206E2681998-08-26026 August 1998
Rev 12 to EM Environ Manual for Wepc
ML20203K3081997-12-0808 December 1997
Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program
ML20203K3231997-12-0202 December 1997
Rev 11 to Draft Odcm
ML20203K3121997-12-0101 December 1997
Rev 12 to Draft Environ Manual Wisconsin Electric
ML20203K3201997-11-25025 November 1997
Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric
ML20140H0171997-05-0101 May 1997
Rev 12 to Training Courses Trcr 86.0, Administrative
ML20140H0321997-05-0101 May 1997
Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program
ML20140G9811997-04-29029 April 1997
Assessment of Corrective Action Program Pbnp
ML20140G9241997-04-11011 April 1997
Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown)
ML20140G8741997-04-0707 April 1997
Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly)
ML20140G9071997-04-0707 April 1997
Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling)
ML20217P2851997-04-0303 April 1997
Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm
ML20140G9031997-03-21021 March 1997
Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown)
ML20140G9741997-03-21021 March 1997
Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded
ML20140G9621997-03-19019 March 1997
Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded
ML20140G9521997-03-17017 March 1997
Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test
ML20140G9131997-03-17017 March 1997
Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling)
ML20140G8821997-03-0404 March 1997
Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly)
ML20140H3401997-02-28028 February 1997
WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11
ML20140H3011997-02-28028 February 1997
WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05
ML20140H3331997-02-28028 February 1997
WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01
ML20140H3241997-02-27027 February 1997
WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03
ML20137P8441997-02-14014 February 1997
Rev 5 to Authorization of Changes,Test & Experiments (10CFR50.59 & 72.48 Reviews)
ML20140G9351997-02-14014 February 1997
Rev 13 to ISTs IT 585, Leakage Reduction & Preventive Maint Program Test of Post-Accident Containment Atmospheric Sampling Sys (Refueling)
ML20140G8921997-02-14014 February 1997
Rev 7 to ISTs IT 215, SI Valves (Cold Shutdown)
ML20140G9401997-02-0707 February 1997
Rev 21 to TS Tests TS 10A, Containment Airlock Door Seal Testing
ML20138K2991997-01-31031 January 1997
Rev 46 to OP 4D,Part 1, Draining RCS to CVCS Hut W/O Entering Reduced Inventory
ML20138K2031997-01-31031 January 1997
Rev 6 to IT 380, Purge Valve Air Sys Check Valve (Quarterly) for Unit 1
ML20138K2551997-01-31031 January 1997
Rev 2 to IT 530B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) for Unit 1
ML20138K2411997-01-31031 January 1997
Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1
ML20138K3231997-01-31031 January 1997
Rev 9 to RP 6A, SG Crevice Flush (Vacuum Mode)
ML20137P8551997-01-31031 January 1997
Brine Tank Standpipe Mod
ML20138K3071997-01-31031 January 1997
Rev 38 to OP 9C, Containment Venting & Purging
ML20138K2901997-01-31031 January 1997
Rev 2 to IT 535A, Leakage Reduction & Preventive Maint Program Test of Train a HHSI & RHR Sys (Refueling) Unit 2
ML20138K2641997-01-31031 January 1997
Rev 12 to IT 535, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 2
ML20138K4991997-01-31031 January 1997
Rev 9 to Ort 4, Main Turbine Mechanical Overspeed Trip Device for Unit 2
ML20138K3181997-01-31031 January 1997
Rev 33 to RP 1B, Recovery from Refueling
ML20138K3031997-01-31031 January 1997
Rev 1 to OP 4D,Part 5, Draining RCS to CVCS Hut W/O Entering Reduced Inventory & W/O SG Tubes
ML20138K2251997-01-31031 January 1997
Rev 7 to IT 385, Purge Valve Air Sys Check Valve (Quarterly) for Unit 2
ML20138K4791997-01-31031 January 1997
Rev 15 to Ort 67, Component Cooling Water to & from Excess Letdown Heat Exchanger-Refueling Shutdown for Unit 1
ML20138K4701997-01-31031 January 1997
Rev 17 to Ort 59, Train Spray Sys CIV Leakage Test for Unit 1
ML20138K5041997-01-31031 January 1997
Rev 7 to Ort 50, PRT to Gas Analyzer Sample Line for Unit 2
ML20138K5161997-01-31031 January 1997
Rev 18 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 2
ML20138K4751997-01-31031 January 1997
Rev 19 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 1
ML20138K5231997-01-31031 January 1997
Rev 7 to Ort 71, Electrical Penetration Leak Test for Unit 2
ML20138K7311997-01-31031 January 1997
Rev 9 to TS 80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175A,B) & EDG Day Tanks (T-31A,B & T-176A,B)(Quarterly)
ML20138K7171997-01-31031 January 1997
Rev 6 to TS 37, Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Yrs) for Unit 1
ML20138K3121997-01-31031 January 1997
Rev 43 to RP 1A, Preparation for Refueling
1998-09-30
[Table view] |
Text
i POINT BEACH NUCLEAR PLANT PBSG 7.2
~ SECURITY GUIDELINES Revision 0
' l January 23,1997 i
VITALIZATION OF UNIT TWO I Date 23/97 SRO Add Security AFaA Mt[ h V
1.0 PURPOSE 1.1 To ensure that no sign of equipment tampering, fire hazards or security discrepancies exist prior to revitalizing the Unit 2 Facade.
1.2 To ensure that a cleanup and removal of foreign materials, debris and non-essential equipment has been completed in the Unit 2 Facade.
NOTE: Personnel responsiblefor cleanup and removal of non-essential equipment have been instructed to be alert to any indication oftampering.
2.0 REFERENCES
.. 2.1 PBNPSP 7.0, SPECIAL SITUATIONS AFFECTING SECURITY.
3.0 PRECAUTION AND LIMITATIONS 3.1 Foreign debris found within the refueling cavity, or around primary openings may be highly radioactive.
3.2 Tools, equipment or materials utilized for performing maintenance, inspection or testing of components in contact with primary system coolant will be handled as potential sources of high levels of contamination.
3.3 All tools and equipment collected, as a result of this inspection, will be i clearly labeled with identification and location found.
3.4 Under no circumstance will unidentified material be handled until it can be l surveyed to quantify its radioactive properties. Ifin doubt, ask Health Physics for assistance.
i 4.0 INTTIAL CONDITIONS l i
l 4.1 An RWP is ready for inspection of all areas within containment. Direct HP !
coverage is suggested, as any material that needs to be removed can be j surveyed by HP and transported out of containment by the inspection team. l Page 1 of 6 i 9703110287 970305 NFORMATION USE PDR ADOCK 05000301 F PDR ,
--.4
. POINT BEACH NUCLEAR PLANT PBSG 7.2 SECURITY GUIDELINES Revision 0 January 23,1997 VITALIZATION OF UNIT TWO 5.0 TOOLS & EOUIPNENT 5.1 The search team will have a flashlight, search mirror and binoculars available during the walkdown.
6.0 WALKDOWN PROCEDURE Enter the areas listed and make a general inspection to ensure that the area is free of non-essential equipment, signs of equipment tampering, fire hazards and security discrepancies. Access to these areas will be limited to the search team and operation personnel, until the search has been completed.
6.1 Search Team Personnel NOTE: Upon completion of the test the CAS shall begin dispatching to all alarms on doors-231 and 232.
6.1.1 Instruct the CAS to:
i t a. Secure doors 231 and 232.
- b. Test doors 231 and 232.
6.1.2 Instruct the control room to make a general announcement that personnel in the Unit 2 Facade should leave the area until the search can be completed.
l 6.2 Areas To Be Searched I
6.2.1 Unit 2 Non-Nuclear Room.
l Remarks: A/dlke, uoose Mohtd J
- a. Upon completion of the search instruct the CAS to take the I card reader and exit switch off-line on door-183. l 1
i
, s, i
l Page 2 of 6 INFORMATION USE l
t
POINT BEACH NUCLEAR PLANT PBSG 7.2 SECURITY GUIDELINES Revision 0 January 23,1997 1
VITALIZATION OF UNIT TWO 6.2.2 Unit 2 Rod Drive Room.
, Remarks: %}ed/Suh m QpAs - --
)
- a. Upon completion of the search instruct the CAS to take the ;
card reader and exit switch o$line on door 172.
6.2.3 Unit 2 Facade exterior walls and barriers. I l
4 Remarks: hh sah Efnb e w '
j stt(IAAflhtA dAmrMAO d !
I l
6.2.4 Unit 2 Facade Roof down to the 66' level hatch and Unit ' i elevator room. )
t
( -
Remarks: l}0$ttki EmLMUA) didMUCMb t
J I
6.2.5 Unit 2 Containment Building.
- a. Post security personnel at the 26' and 66' level hatches, to i limit access to the search team and operations personnel during the search.
- b. Instruct the CAS to take the card readers and exit switches o5line on doors 141,156,173 and 319.
- c. Ser.rch the areas:
e On top of the polar crane.
. "A" loop which includes all levels of the steam generator and reactor coolant pump companments, all walkways, and the El.10' platform.
Page 3 of 6 INFORMATION IJSE
o ' POINT BEACH NUCLEAR PLANT PBSG 7.2 SECURITY GUIDELINES Revision 0 January 23,1997 VITALIZATION OF UNIT TWO All levels of the pressurizer compartment.
. "B" loop which includes all levels of the steam generator and reactor coolant pump compartment, all walkways, and the El.10' platform.
NOTE: Binocular inspection of the upper and lower cavities is acceptable.
. The reactor cavity.
. El. 66' general area.
. El. 46' general area. *
The regenerative heat exchanger compartment.
Remarks: 5/ M Anff.eA M j d i a d iAA14. Antall a+1tDaAtL A /AvthalriNe mtabsikt.L laddW t ALkt dA& tw u% Mim m
- 6.2.6 htwsut & t%{sud.
Unit 2 Fan Room.
Remarks: W dAU1ALULA di6 cat}OtDL$ .
G
- a. Upon completion of the search, instruct security personnel to provide access control into the Unit 2 Facade. Post security personnel at the:
. 26' level hatch to monitor door 232.
. 66' level hatch to monitor door 193.
6.2.7 Unit 2 Facade general area.
- a. 66' level.
- b. 52' level,
- c. 26' level.
- d. 6.5' level.
Remarks: R 4 U R u d l d $ C # fl D t1 d V
Page 4 of 6 LNFORMATION USE
, o
' POINT BEACH NUCLEAR PLANT PBSG 7.2 SECURITY GUIDELINES Revision 0 Januarj 23,1997 VITALIZATION OF UNIT TWO 7.0 DECLARE UNIT 2 FACADE VITAL 7.1 Upon completion of a satisfactory search, the WE security supervision search team member will declare the Unit 2 Facade a vital area. Instruct the CAS to make an announcement on the gai-tronic about the status change in to the Unit 2 Facade.
7.2 Instmct the CAS operator to put the card readers and exit switches on-line for doors 141,156,172,173,183 and 319.
7.3 Terminate the compensatory measure at the 26' & 66' containment hatches.
7.4 Send an E-mail to all plant personnel noting the change in status of the Unit 2 "acade.
7.5 Issue procedure changes to PBSRP 2.1, PBSRP 2.8 and forms Sec-40ag, SEC-40g, and SEC-88. Remove PBSG 7.1 from the guideline manual.
-< 8.0 RESTORATION OF SECURITY CONDITION 2 DOORS l
l 8.1 Perform the following actions for doors 141,142,155 and 156:
8.1.1 Rename the doors as fire doors.
8.1.2 Test the doors.
8.1.3 Instruct the CAS to start dispatching to alarms on the doors.
8.2 Perform the following actions for doors 173,193, and 319.
8.2.1 Access the doors.
8.2.2 Rename the doors as group 10 doors.
8.3 Physically unlock doors 141,142,155,156,173, I?3, and 319.
s' Page 5 of 6 INFORMATION IISE
POINT BEACH NUCLEAR PLANT PBSG 7.2 SECURITY GUIDELINES Revision 0 January 23,1997 VITALIZATION OF UNIT TWO
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