|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18152B3591999-08-23023 August 1999
Revised Tech Specs Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in UFSAR & Includes Ref to Applicable UFSAR Section
ML18151A6641999-08-0606 August 1999
Rev 0 to Surry Unit 2 Cycle 16 Startup Physics Tests Rept.
ML18152B6591999-04-28028 April 1999
Proposed Tech Specs Re Refueling Water Chemical Addition Tank Min Vol
ML18152B5451999-02-16016 February 1999
Proposed Tech Specs Pages,Revising Augmented Insp Requirements for Reactor Coolant Pump Flywheels
ML18152A2131999-02-16016 February 1999
Proposed Tech Specs,Consolidating AFW cross-connect Requirements by Relocation of Electrical Power Requirements from TS 3.16 to TS 3.6
ML18151A5511999-02-10010 February 1999
to NE-1187, Surry Unit 1,Cycle 16 Startup Physics Tests Rept.
ML18152B6151998-11-0404 November 1998
Proposed Tech Specs 4.6.A.1.b,re EDG Start & Load Time Testing Requirements & TS 3.16 Bases Re EDG Ratings
ML18153A3351998-09-24024 September 1998
Proposed Tech Specs Pages Affected by Suppl to 960912 Resubmittal of Change Request Re Relocation of Fire Protection Requirements from TS to UFSAR
ML18153A3311998-09-24024 September 1998
Proposed Tech Specs Modifying Testing Requirements for Reactor Trip Bypass Breaker
ML18152B7551998-06-19019 June 1998
Proposed Tech Specs Establishing Requirements for Use of Temporary Supply Line (Jumper) to Provide Svc Water to Component Cooling Heat Exchangers
ML20249B9911998-05-0606 May 1998
Analysis of Capsule X Virginia Power Surry Unit 1 Reactor Vessel Matl Surveillance Program. W/Evaluation of Surry Unit 1 Surveillance Capsule X Results & Response to NRC RAI Re GL 92-01,rev 1,suppl 1
ML18151A1931998-05-0404 May 1998
Rev 1 to Summary of Changes to Surry Units 1 & 2 Third Interval IST Program.
ML18152A3651998-03-25025 March 1998
Proposed Tech Specs Revising Station Mgt Titles to Reflect New Positions Approved by Vepc Board of Directors on 980220
ML20199B0711998-01-0505 January 1998
Rev 0 to NE-1148, Surry Unit 2,Cycle 15 Startup Physics Test Rept
ML18153A3481997-12-18018 December 1997
Proposed Tech Specs Clarifying Terminology Used for Describing Equipment Surveillances Conducted on Refueling Interval Frequency.Clarification Consistent W/Info Contained in Rev 1 to NUREG-1431
ML18150A4661997-12-16016 December 1997
ISI Plan for Third Insp Interval,Vol 2,Rev 9 for Components & Component Supports,940510-040510, for Surry Power Station,Unit 2
ML18153A3941997-11-0505 November 1997
Proposed Tech Specs Re Change for Increased Enrichment of Reload Fuel
ML18153A1761997-11-0505 November 1997
Proposed Tech Specs Re Temporary Svc Water Supply Line to Component Cooling Heat Exchangers
ML18150A4641997-10-27027 October 1997
Risk-Informed ISI (RI-ISI) Pilot Program Submittal.
ML18151A3911997-10-16016 October 1997
Rev 8 to VPAP-2103, Odcm.
ML18151A7231997-08-0707 August 1997
Rev 1 to Nuclear Safety Analysis Manual Part Iv,Chapter a Probabilistic Safety Assessment Products.
ML20210J5031997-07-31031 July 1997
Rev 0 to NE-1132, Surry Unit 1,Cycle 15 Startup Physics Tests Rept
ML18150A4441997-06-0909 June 1997
Vol 2,Rev 8 to ISI Plan for Third Insp Interval for Components & Component Supports,Oct 14,1993-Oct 13,2003.
ML18153A5231997-04-24024 April 1997
Proposed Corrected Tech Specs Pages 6.1-3 & 6.1-8 Re Relocation of Fire Protection TS to Updated Final Safety Analysis Rept
ML18153A5031997-03-18018 March 1997
Proposed Tech Specs Rev to Section 4.15 for Surry Power Station to Include Pp Inadvertently Omitted from 970203 Request for Amend to Licenses DPR-32 & DPR-37
ML18153A4921997-02-0303 February 1997
Proposed Tech Specs Re Deletion of Specific ASME Section XI Code Ref
ML18153A6351996-11-26026 November 1996
Proposed Tech Specs Re Removal of Record Retention Requirements,Per GL 95-06 & Administrative Ltr 95-06
ML18153A0671996-09-12012 September 1996
Proposed Tech Specs Re Relocation of Fire Protection Requirements
ML18151A9761996-08-13013 August 1996
Cycle 14 Startup Physics Test Rept. W/960830 Ltr
ML20134J9861996-07-30030 July 1996
/Unit 2 Fuel Assembly Insp Program
ML18152A4701996-06-13013 June 1996
Cycle 13 Control Rod Performance Test Results.
ML18153A6901996-04-15015 April 1996
Proposed Tech Specs,Clarifying Applicability of Quadrant Power Tilt Ration Requirements
ML18153A5391996-03-21021 March 1996
Proposed Tech Specs Re Charcoal Filter Testing Clarification
ML18153A5271996-03-14014 March 1996
Proposed Tech Specs,Permitting Use of 10CFR50 App J,Option B,performance-based Containment Lrt
ML18153A5801996-01-30030 January 1996
Proposed Tech Specs Re Reactor Coolant Sys Liquid Sampling
ML18152A0571995-12-20020 December 1995
Startup Physics Test Rept,Surry Unit 1,Cycle 14. W/960111 Ltr
ML18153A6761995-11-20020 November 1995
Proposed Tech Specs Re App J Option B,performance-based Containment Leakage Rate Testing
ML18151A6421995-08-0101 August 1995
Change 3 to Rev 0 to Third Interval IST Program
ML18153A7141995-07-20020 July 1995
Proposed Tech Specs Establishing New Setpoint Limit for SG high-high Level & Provides More Restrictive Setting Limits for Certain Rps/Esfas Setpoints
ML18153A6991995-07-14014 July 1995
Proposed Tech Specs,Providing Two H Allowed Outage Time for One RHR Pump to Accommodate Plant Safety,Emergency Power Sys Surveillance Testing & Permit Depressurizing SI Accumulators in Lieu of Accumulator Isolation
ML18153A8371995-06-0808 June 1995
Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Associated Ltops Setpoint That Will Be Valid to end-of-license
ML20083C9951995-05-0808 May 1995
Rev 0 to Surry Unit 2,Cycle 13 Startup Physics Tests Rept
ML18153B2301995-02-14014 February 1995
Proposed Tech Specs Re App J Testing Requirements
ML18153B2131995-01-24024 January 1995
Proposed Tech Specs,Modifying as-found Test Acceptance Criterion for Pressurizer Safety Valves
ML18153B1621994-11-29029 November 1994
Proposed Tech Specs Implementing Zirlo Fuel Cladding
ML18153B1581994-11-22022 November 1994
Proposed Tech Specs,Deleting Unnecessary Descriptive Phrases Re Number of Cells in Station & EDG Batteries
ML18153B1501994-11-10010 November 1994
Proposed Tech Specs Re Changes to TS Will Clarify SR for Reactor Protection & Engineered Safeguard Sys Instrumentation & Actuation Logic
ML18153B0941994-10-11011 October 1994
Proposed Tech Specs Surveillance Frequencies for Hydrogen Analyzers
ML18152A5061994-09-0606 September 1994
Proposed Tech Specs Re Mgt Safety Review Committee & Station Nuclear Safety & Operating Committee Responsibilities
ML18152A1191994-08-30030 August 1994
Proposed Tech Specs to Accomodate Core Uprating
1999-08-06
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18151A1931998-05-0404 May 1998
Rev 1 to Summary of Changes to Surry Units 1 & 2 Third Interval IST Program.
ML18150A4661997-12-16016 December 1997
ISI Plan for Third Insp Interval,Vol 2,Rev 9 for Components & Component Supports,940510-040510, for Surry Power Station,Unit 2
ML18150A4641997-10-27027 October 1997
Risk-Informed ISI (RI-ISI) Pilot Program Submittal.
ML18151A3911997-10-16016 October 1997
Rev 8 to VPAP-2103, Odcm.
ML18151A7231997-08-0707 August 1997
Rev 1 to Nuclear Safety Analysis Manual Part Iv,Chapter a Probabilistic Safety Assessment Products.
ML18150A4441997-06-0909 June 1997
Vol 2,Rev 8 to ISI Plan for Third Insp Interval for Components & Component Supports,Oct 14,1993-Oct 13,2003.
ML20134J9861996-07-30030 July 1996
/Unit 2 Fuel Assembly Insp Program
ML18151A6421995-08-0101 August 1995
Change 3 to Rev 0 to Third Interval IST Program
ML20076F8341994-08-0404 August 1994
Rev 0,Change 1 to Surry Unit 2 Third Interval IST Program
ML18151A2451994-07-31031 July 1994
ISI Program,Interval 3,940510-040509, for Surry Power Station,Unit 2,rev 1
ML18151A2101994-07-31031 July 1994
ISI Program,Interval 3,931014-031013, Rev 1
ML18151A9011994-03-0303 March 1994
ISI Program Interval 3,940510- 040509, Rev 0
ML18151A1651993-04-30030 April 1993
Rev 0 to Surry Power Station Unit 1 ISI Program Interval 3 931014-031013.
ML18151A6411992-03-19019 March 1992
Rev 5 to Surry Power Station,Unit 1,Inservice Testing Program Plan for Pumps & Valves,Second Insp Interval 821222-921222.
ML18151A3711992-03-19019 March 1992
Rev 3 to Surry Power Station,Unit 2 Inservice Testing Program Plan for Pumps & Valves,Second Insp Interval 821222-921222.
ML20079L2091991-09-22022 September 1991
Rev 2 to Station Administrative Procedure VPAP-0805, MOV Program, Upgrading Procedure to Acup Format
ML20092M9061991-09-0101 September 1991
Rev 2 to VPAP-2103, Odcm
ML18151A4121991-09-0101 September 1991
Rev 2 to VPAP-2103, Odcm.
ML18151A6551990-11-14014 November 1990
Revised Corporate Emergency Plan Implementing Procedures, Including Rev 0 to CPIP-1.0,CPIP-2.0,CPIP-2.1,CPIP-2.2, CPIP-2.3,CPIP-2.4,CPIP-2.5,CPIP-2.6,CPIP-3.0,CPIP-3.1 & CPIP-3.2
ML20006C0571990-01-18018 January 1990
Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan.
ML16152A8951990-01-0202 January 1990
Rev 33 to Public Version of Crisis Mgt Plan for Nuclear Stations.
ML15264A1571990-01-0202 January 1990
Revised Crisis Mgt Implementing Procedures,Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9,Rev 1 to CMIP-14 & Rev 30 to CMIP-21
ML20012A3801990-01-0101 January 1990
Rev 28 to, Offsite Dose Calculation Manual,Oconee,Mcguire & Catawba Nuclear Stations.
ML20012A3791990-01-0101 January 1990
Rev 27 to, Offsite Dose Calculation Manual,Oconee Nuclear Station.
ML20012A3771990-01-0101 January 1990
Rev 26 to, Offsite Dose Calculation Manual McGuire Nuclear Station.
ML20012A3751990-01-0101 January 1990
Rev 25 to, Offsite Dose Calculation Manual,Cawtaba Nuclear Station.
ML20012A3691989-12-0505 December 1989
Rev 8 to, Process Control Program,Mcguire Nuclear Station.
ML20011D2441989-12-0101 December 1989
Crisis Mgt Implementing Procedures.
ML20012A3721989-11-27027 November 1989
Rev 4 to, Process Control Program,Cawtaba Nuclear Station.
ML20012A3731989-11-15015 November 1989
Rev 4 to, Process Control Program Oconee Nuclear Station.
ML19332C8451989-11-0101 November 1989
Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 31 to CMIP-1,Rev 28 to CMIP-4,Rev 32 to CMIP-5,Rev 37 to CMIP-6,Rev 36 to CMIP-7,Rev 25 to CMIP-8,Rev 31 to CMIP-9 & Rev 19 to CMIP-13
ML19325F1931989-11-0101 November 1989
Public Version of Rev 32 to, Crisis Mgt Plan for Nuclear Stations.
ML20247H3371989-09-15015 September 1989
Revised Corporate Organization for Nuclear Incidents (Coni) Procedure Manual Including Rev 15 to CONI-1.01, Preparation,Issuance & Control Procedures, Rev 30 to CONI-1.02, Coni & Rev 19 to CONI-1.03, Alerting ..
ML20245L7651989-08-0707 August 1989
Rev 0 to Offsite Dose Calculation Manual
ML20247M7921989-07-31031 July 1989
Rev 6 to PWR Operations Guideline Number 12 Simulator Testing Program. Simulator Transient Test Review Data Encl
ML20247M9151989-07-27027 July 1989
Procedure Generation Package
ML20247N0421989-06-19019 June 1989
Rev 5 to SS-1, Braidwood Simulator Steady State Performance Test
ML20247M7861989-05-26026 May 1989
Rev 0 to SV-1, Braidwood Simulator Surveillance Testing
ML20247M7581989-05-26026 May 1989
Rev 0 to Test NO-1, Braidwood Simulator Normal Operations Testing
ML18152A5231989-04-19019 April 1989
Rev 0 to Motor-Operated Valve Action Plan.
ML20245C2541989-04-0505 April 1989
Public Version of Rev 29 to Duke Power Co Crisis Mgt Plan for Nuclear Stations
ML20247M7801989-04-0404 April 1989
Rev 0 to ST-1 Re Simulators safety-related Valves Stroke W/ Acceptable Time Period Required by ANSI/ANS-3.5-1985
ML20247M8741989-02-0101 February 1989
Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2
ML20247M8661989-02-0101 February 1989
Rev to 1BEP-0, Reactor Trip or Safety Injection Unit 1
ML20247M8201989-02-0101 February 1989
Rev 1 to 2BWEP-0, Reactor Trip or Safety Injection Unit 2
ML20247M8011989-02-0101 February 1989
Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1
ML18152A2911988-10-19019 October 1988
Major Milestones Description of Issue Approach to Resolution.
ML20204J1391988-09-0707 September 1988
Temporary Procedure Change 88-504 to Rev 4 to Procedure E-0, Reactor Trip or Safety Injection
ML20204J0391988-08-23023 August 1988
Rev 4 to Emergency Operating Procedure EOP 3.1-28, Turbine Overspeed
ML20205A6651988-08-0303 August 1988
Rev 3 to Emergency Operating Procedure EOP 2540D, Functional Recovery of Heat Removal
1998-05-04
[Table view] |
Text
TRANSDUCERS*
ELECTRONICS P.O. Box 9025
- 8626 Wilbur Avenue Northridge, California 91328 T~lephone (213) 886-8488 Telex 65-1303 INSPECTION RECORD CHECKLIST FOR
REFERENCE:
PROCEDURE NO. ¥6&, VALIDYNE ORDER NO. 9179 PROCEDURE REV-. ----6---ADDENDUM:
- 12. DATE : _ _./'-,;O;;;....;-Z:::.-...1S-..i..{
__ _ EVENT/OPERATION DESCRIPTION:_---'S--=E~l~S~M
........ 1-C....._
_____________
__ NOMENCLATURE:
REl'/OTE MUL7/PLEXEE!_
QUANTITY:
__ ! __ PART NUMBERS: J.1C.J7{)
AIJ-Q& SERIAL NUMBERS: __ 5=-,,4_,Z=--7
__ 8 _____ _ MC37D A,;n -92.r 5 o/ il Z 9 I. INITIAL VERIFICATION Prior to testing, verify the following:
- a. Previous operations and inspections required by the Traveler have been completed
- b. Procedure and revision level is co~rect. c. Applicable drawings and revision status is in accordance with configuration requirements.
- d. Equipment and monitoring devices used for testing are within calibration due dates. II. PHYSICAL INSPECTION Upon completion of testing, inspect for the following conditions in accordance with the drawing: a. Part number, serial number and revision level is correct. b. -There is no evidence of damage such as cracks, dents, functional type interference between parts, burns or dEtformation.
- c. Hardware is secure. d. Electrical connection integrity.
INSPECTI9N RESULTS: There was no visible evidence of damage unless noted below. V V~!!~t~! INSTRUMENTATION
- ELECTRONICS P.O. Box 9025 *
- 8626 Wilbur Avenue Northridge, California 91328 Telephone (213) 886-8488 Telex 65-1303 INSPECTION RECORD CHECKLIST FOR
REFERENCE:
PROCEDURE NO. 7't:, (p VALIDYNE ORDER NO. CJ/ 7 CJ PROCEDURE REV. -G-ADDENDUM:
JZ, DATE: IO I EVENT/OPERATION DESCRIPTION:
EXTl<EME TEMP U/UM I PtTY TE$ T --==..:.~..i.:::.t..;....M---:..-=.:...u.-,~~.;.i;..,,.
....... __._ _ __._~"'-'----
NOMENCLATURE:
REP!OTE MULTIPLEXER.
QUANTITY:_......;..., __ PART NUMBERS: MC. 170 A:rJ-06,( SERIAL NUMBERS: ____ S ___ ?"'.:...,:Z
... 7;....aB ___ _ MC 3 za I/ n -Q 2 s '-i il Z q I. INITIAL VERIFICATION Prior to testing, verify the following:
- a. Previous operations and inspections required by the Traveler have been completed.
- b. Procedure and revisi~n level is correct. c. Applicable drawings and revision status is in accordance with configuration requirements.
- d. Equipme~t and monitoring devices used for testing are within calibration due dates. II. PHYSICAL INSPECTION Upon completion of testing, inspect for the following conditions in accordance with the drawing: a. Part number, serial number and revision level is correct. b. There is no evidence of damage such as cracks, dents, functional type interference between parts, burns or de-formation.
- c. Hardware is secure. d. Electrical connection integrity.
--+:::::: INSPECTO~~
~,~,! DATE: ltJ-9-PJ ACCEPTABILITY:
\J;J 'llj, INSPECTION RESULTS: There was no visible evidence of damag~ unless noted below.
INSTRUMENTATION*
TRANSDUCERS*
ELECTRONICS P.O. Box 9025
- 8626 Wilbur Avenue Northridge, California 91328 Telephone (213) 886-8488 Telex 65-1303 INSPECTION RECORD CHECKLIST FOR
REFERENCE:
PROCEDURE NO. L./fofo VALIDYNE ORDER NO. q 17 'l PROCEDURE REV. ADDENDUM:
/2 DATE: 10-9-Bf EVENT/ OPERATION DESCRIPTION
- _...:E:..;;.'X.:..T;.;;~.::E:.;.M..:.:E.~T-=E:.:.M..:.:..P..1,/...:H~U.;..M.;.,;1;..::D:::.:l:..:.T...:Y~T..;..:E;.::S:..:.~-----
NOMENCLATURE
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.... L-=E.:aaa..=S
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PART NUMBERS: SEE P.AC.E 2 1:'3 SERIAL NUMBERS: ..SEE. PIU,,=. I. INITIAL VERIFitATION Prior to testing, verify the following:
- a. Previous operations and inspections required by the Traveler havs been completed. . b. Procedure and revision level is correct. c. Applicable drawings and revision status is in accordance with configuration requirements.
- d. Equipment and monitoring devices used for testing are within calibration due dates~ II.. PHYSICAL INSPECTION Upon completion of testing, inspect for the following conditions in accordance with the drawing: a. Part number, serial number and revision level is correct. b. There is no evidence of damage such as cracks, dents, functional type interference between parts, burns or deformation.
- c. Hardware is secure. d. Electrical connection integrity.
INSPECTO~~~
INSPECTION RESULTS: There was no visible evidence of dama~e unless noted below. ..2 £'3 I -. -....
... AlidyNE ENQINEEIIINQ COIIPOIIATION INSPECTION RECORD CHECKLIST Page 2 of 3 PROCEDURE NO. '/'ttI, PROCEDURE REV. -I)-NOMENCLATURE:
PLUG-IN MODULES DATE: /i!J-f-RI INITIAL PHYSICAL MODEL NUMBER SERIAL NUMBER VERIFICATION INSPECTION AB295-Q2 QS981-l t,..-_., . QS981-2 t/ -AD296-2-Q2 QS982-l V --QS982-2 __!:;_ -PT174-2-Q2 Q9702-5-l V v' Q9702-S-2
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-PS171;.Q2 QE 543-56 28 7 v ,,,., QE543-56288
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(. AlidyNE ENOINl!EfllNQ COflPOflATION INSPECTION RECORD CHECKLIST Page 3 of 3 PROCEDURE NO. ¥&;£ PROCEDURE REV. -e-NOMENCLATURE:
PLUG-IN MODULES DATE: /0-9-91 INITIAL PHYSICAL MODEL NUMBER SERIAL NUMBER VERIFICATION INSPECTION CDl 73-Q2 QE538-l ..--....... 'QE538~2 -QE428-21 ,....,-QE428-22 CM249-Q2 55420 */ .,/ 55421 ____i::::::: 55422 .......!:::.. 55423 ,,,..... -==::::... PS324-Q2 56460 V' v--56461 ----IL
~-------------
~----.. * ( * (. REPORT OF COMPLIANCE Procedure Nmnber: Procedure Rev: 0 --~---Validyne Order No: 9/ 7 9 Addendum:
12... ~XTR~H~ ~EMPERA-,VRE/
HUMIDrry T1aosr this report is certification that testing operations contained in the above procedure were completely and carefully conducted-on this day of* q , 19 81 , and were witnessed
To the best of my knowledge, the above statement is true and correct. (Date) VAL1Dt:AJe.
eAJa. (Organization)
/0-f. II I (Date)
*. ------------REPORT OF COMPLIANCE Procedure Number: Procedure Rev: Validyne Order No: Addendum:
0 1 C. Sf:C.TION I! ON'-Y g1:;1SM IC. TS:>T This report is certification that testing operations contained in the above procedure were completely and carefully conducted on this day of OCTOBE~ I -e , 19 g I , and were witnessed by the undersigned.
To the best* of my knowledge, the above statement is true and correct. -. (Title)* 10-z-s, (Date) (Organization) 10-?-fll (Date) WY1E. LA 130R..ATOR 1es (Organization)
REVl&IONa SYM DESCRIPTION DATE ELECTRICAL CONTACT AND CONTROL REWORK PROCEDURE Step 1. Detennine if the device operates properly.
If not, then follow the following steps to clean the device contacts or controls.
Step 2. Spray device through available openings to contacts or controls using control cleaner and lubricant, VEC Part No. F262-231S.
Then operate the device ten times. Step 3. Repeat Step 2 at least two or three times or until the device is working normally.
APl9ROVAL MFG. ENGRG. APPROVAL:_12./;L_,-;-_~~-----
ENGRG. APPROVAL:
}~---------=:::;_....---=---'-----
NOTES: UNLESS OTHERWISE SPECIFIED.
CODE IDENT NO 33107 TOL. UNLESS NOTED DEC.XXX FRAC. & DEC. XX ANGLES +/- 1/2° DIAMETERS WITH SAME t SHALL BE CENTRIC WITHIN .005 TIR. SURFACES MUST BE FLAT WITHIN .002 PER IN. MAX FILLET .015 UNLESS NOTED. DEBURR EDGES .005 MAX UNLESS NOTED. SURFACE FINISH -W UNLESS NOTED. DRILLED HOLE TOL. PER AND10387.
SCALE OWN CK'D APPVD. TITLE JK / 1/ 8 MODEL MAT'L FINISH ELECTRICAL CONTACT AND CONTROL REWORK PROCEDURE