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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217F9701999-10-14014 October 1999
Proposed Tech Specs,Incorporating ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plate Intersections
ML20217E4301999-10-12012 October 1999
Proposed Tech Specs,Revising Requirements for Containment Penetrations During Refueling Operations
ML20211M7341999-08-30030 August 1999
Marked-up & Revised TS Pages,Providing Alternative to Requirement of Actually Measuring Response Times
ML20211K1721999-08-30030 August 1999
Proposed Tech Specs,Providing Clarification to Current TS Requirements for Containment Isolation Valves
ML20209B7731999-06-30030 June 1999
Proposed Tech Specs Updating Requirmements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431
ML20196F2211999-06-24024 June 1999
Proposed Tech Specs Pages for Amend to Licenses DPR-77 & DPR-79,allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters
ML20196G4701999-06-24024 June 1999
Proposed Tech Specs Pages Re Amends to Licenses DPR-77 & DPR-79,revising TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431
ML20196G7961999-06-22022 June 1999
Proposed Tech Specs Bases,Clarifying Proper Application of TS Requirements for Power Distribution Systems & Functions That Inverters Provide to Maintain Operability & Providing Updated Info on Cold Leg Injection Accumulators
ML20196G8071999-06-22022 June 1999
Revs to Technical Requirements Manual
ML20195E9841999-06-0707 June 1999
Proposed Tech Specs,Increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core
ML20206E1611999-04-29029 April 1999
Proposed Tech Spec Change 99-04, Auxiliary Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance
ML20206E1391999-04-29029 April 1999
Proposed Tech Spec Change 99-03, Main Control Room Emergency Ventilation Sys Versus Radiation Monitors. Changes Add LCOs 3.3.3.1 & 3.7.7 to Address Inoperability of Radiation Monitoring CREVS & NUREG-1431 Recommendations
ML20204E8501999-03-21021 March 1999
Plant,Four Yr Simulator Test Rept for Period Ending 990321
ML20204H4081999-03-19019 March 1999
Proposed Tech Specs,Relocating TS 3.8.3.1,3.8.3.2,3.8.3.3 & Associated Bases Associated with Electrical Equipment Protective Devices to Technical Requirements Manual
ML20207D6331999-02-26026 February 1999
Proposed Tech Specs Providing for Consistency When Exiting Action Statements Associated with EDG Sets
ML20207D6011999-02-26026 February 1999
Proposed Tech Specs Relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM
ML20206S0131999-01-15015 January 1999
Proposed Tech Specs 3.3.3.3, Seismic Instrumentation & Associated Bases,Relocated to Plant Technical Requirements Manual
ML20199K6001999-01-15015 January 1999
Proposed Tech Specs Adding New Action Statement to 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Appropriate Overall Level of Protection
ML20195H6111998-11-16016 November 1998
Proposed Tech Specs Revising EDG SRs by Adding Note That Allows SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Certain Lockout Features Prevent EDG Starting
ML20154H7251998-10-0808 October 1998
Proposed Tech Specs Pages,Supplementing Proposed TS Change 96-08,rev 1 to Add CRMP to Administrative Controls Section & Bases of TS
ML20238F1091998-08-27027 August 1998
Proposed Tech Specs Providing for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core
ML20238F3001998-08-27027 August 1998
Proposed Tech Specs Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of EDGs
ML20209J1631998-08-0707 August 1998
Rev 41 to Sequoyah Nuclear Plant Odcm
ML20236G5961998-06-29029 June 1998
Proposed Tech Specs Typed Pages for TS Change 95-19, Section 6 - Administrative Controls Deletions
ML20249C6371998-06-26026 June 1998
Proposed Tech Specs Lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05
ML20248F0051998-05-28028 May 1998
Proposed Tech Specs for Section 6, Administrative Controls Deletions
ML20217N3511998-04-30030 April 1998
Proposed Tech Specs Pages,Modifying Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4
ML20203J1681998-02-25025 February 1998
Proposed Tech Specs Pages,Revising EDG Surveillance Requirements to Delete Requirement for 18-month Insp IAW Procedures Prepared in Conjunction W/Vendor Recommendations & Modify SRs Associated W/Verifying Capability of DGs
ML20202J7651998-02-13013 February 1998
Technical Requirements Manual
ML20202J7141998-02-13013 February 1998
Proposed Tech Specs Adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves
ML20202J6961998-02-13013 February 1998
Proposed Tech Specs Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431)
ML20202J7601998-02-13013 February 1998
Proposed Tech Specs Section 3.7.9 Re Relocation of Snubber Requirements
ML20198T4311998-01-21021 January 1998
Proposed Tech Specs Re New Position Title & Update of Description of Nuclear Organization
ML20199F8231997-11-30030 November 1997
Cycle 9 Restart Physics Test Summary, for 971011-971130
ML20199K4571997-11-21021 November 1997
Proposed Tech Specs Adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required
ML20211A3191997-09-17017 September 1997
Proposed Tech Specs Re Pressure Differential Surveillance Requirements for Containment Spray Pumps
ML20203B9731997-08-0505 August 1997
Rev 1 to RD-466, Test & Calculated Results Pressure Locking
ML20217J5581997-07-31031 July 1997
Cycle Restart Physics Test Summary, for Jul 1997
ML20210J1671997-04-30030 April 1997
Snp Unit 1 Cycle 8 Refueling Outage Mar-Apr 1997,Results of SG Tube ISI as Required by TS Section 4.4.5.5.b & Results of Alternate Plugging Criteria Implementation as Required by Commitment from TS License Condition 2C(9)(d)
ML20137T0871997-04-0909 April 1997
Proposed Tech Specs Re Elimination of Cycle 8 Limitation for SG Alternate Plugging Criteria
ML20137M8581997-04-0101 April 1997
Proposed Tech Specs 2.1 Re Safety Limits & TS 3/4.2 Re Power Distribution Limits
ML20137C8421997-03-19019 March 1997
Proposed Tech Specs Re Conversion from Westinghouse Electric Corp Fuel to Framatome Cogema Fuel
ML20136J0381997-03-13013 March 1997
Proposed Tech Specs Section 5.6.1.2,revising Enrichment of Fuel for New Fuel Pit Storage Racks
ML20134P8631997-02-14014 February 1997
Proposed Tech Specs Requesting Discretionary Enforcement for 48 Hours Which Is in Addition to 72 Hours Allowed Outage Time Provided by TS Action 3.8.1.1.b
ML20134K9981997-02-0707 February 1997
Proposed Tech Specs Revising TS Change Request 96-01, Conversion from W Electric Corp Fuel to Framatome Cogema Fuel (MARK-BW-17), to Ensure That Core Analysis Computer Code Output Actions Are Consistent W/Hot Channel Factor SRs
ML20138F2581997-01-17017 January 1997
Rev 39 to Sequoyah Nuclear Plant Odcm
ML20134L9261996-11-0808 November 1996
Proposed Tech Specs Re Placing of Channel in Trip for Reactor Trip & Engineered Safety Feature Instrumentation Sys Solely to Perform Testing as Not Requiring Channel to Be Declared Inoperable
ML20129D2661996-10-18018 October 1996
Proposed Tech Specs,Removing Existing Footnotes That Limit Application of Apc for Plant S/G Tubes to Cycle 8 Operation for Both Units
ML20129G7301996-09-26026 September 1996
Proposed Tech Specs 3/4.3.3 Re Fire Detection instrumentation,3/4.7.11 Re Fire Suppression Systems & 3/4.7.12 Re Fire Protection Penetrations
ML20134J9991996-09-23023 September 1996
Fuel Assembly Insp Program
1999-08-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196G8071999-06-22022 June 1999
Revs to Technical Requirements Manual
ML20209J1631998-08-0707 August 1998
Rev 41 to Sequoyah Nuclear Plant Odcm
ML20202J7651998-02-13013 February 1998
Technical Requirements Manual
ML20138F2581997-01-17017 January 1997
Rev 39 to Sequoyah Nuclear Plant Odcm
ML20134J9991996-09-23023 September 1996
Fuel Assembly Insp Program
ML20138F2531996-02-23023 February 1996
Rev 38 to Sequoyah Nuclear Plant Odcm
ML20108B4121995-11-0303 November 1995
Rev 37 to Sequoyah Nuclear Plant Odcm
ML20094Q2301995-10-30030 October 1995
ASME ISI Valve Testing Program Basis Document, Rev 0
ML20094Q1931995-10-30030 October 1995
Rev 1 to ASME Sys Pressure Testing Program Basis Document
ML20094Q1971995-10-30030 October 1995
Rev 1 to SG Tubing ISI & Augmented Insps, Rev 1 to 0-SI-SXI-068-114.2
ML20094Q2111995-10-30030 October 1995
Rev 1 to ASME ISI Pump Testing Program Basis Document
ML20094Q1761995-10-13013 October 1995
ASME Section XI Isi/Nde & Augmented Nondestructive Exam Programs, SSP-6.10,rev 2
ML20094Q1841995-10-13013 October 1995
ASME Section XI Isi/Nde Program Units 1 & 2, Rev 0 to 0-SI-DXI-000-114.2
ML20149L6811994-09-30030 September 1994
Concerns Resolution Program - Sequoyah Nuclear Plant
ML20063D6691994-01-24024 January 1994
Rev 4 to Sequoyah Nuclear Plant Restart Plan
ML20065Q6251993-10-13013 October 1993
Rev 31 to Sequoyah Nuclear Plant Odcm
ML20056F3181993-08-20020 August 1993
Rev 0 of Post-Restart Plan
ML20056G1841993-08-10010 August 1993
Rev 2 to Sequoyah Nuclear Plant Restart Plan
ML20044F3081993-05-20020 May 1993
Rev 0 to Sequoyah Nuclear Plant Restart Plan.
ML18036B1961993-01-27027 January 1993
Rev 2 to Nuclear Power Training Procedure TRN-31, Fire Brigade Training.
ML20127P5461992-12-16016 December 1992
Rev 20 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program,Unit 1
ML20127P6361992-12-16016 December 1992
Rev 19 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program,Unit 2
ML20114C8131992-04-17017 April 1992
Rev 27 to Odcm
ML20101F2081992-02-0808 February 1992
Rev 16 to Surveillance Instruction SI-114.2, ASME Section XI ISI Program Unit 2
ML20101F2011992-02-0808 February 1992
Rev 17 to Surveillance Instruction SI-114.1, ASME Section XI ISI Program Unit 1
ML19332D2241989-09-22022 September 1989
Rev 23 to Odcm.
ML20245H1421989-08-15015 August 1989
Rev 22 to Offsite Dose Calculation Manual Changes
ML20246H4861989-05-16016 May 1989
Rev 1 to Technical Instruction TI-115, Instructions for Sewage Mgt
ML20244E2521989-04-28028 April 1989
Rev 14 to Surveillance Instruction SI-114.2, ASME Section XI Inservice Insp Program
ML20246E7771989-04-25025 April 1989
Rev 14 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program
ML20206D3421988-10-15015 October 1988
Rev 13 to Surveillance Instruction SI-114.2, Inservice Insp Program
ML20154J3221988-09-0909 September 1988
Procedure EA-OR-003-S, Sequoyah Nuclear Plant - Unit 1 Design Baseline & Verification Program,Supplemental Engineering Assurance Oversight Review Rept
ML20150F9291988-06-17017 June 1988
Diesel Generator Voltage Response Improvement Plan
ML20154L1421988-05-0909 May 1988
Rev 3 to Revised Sequoyah Nuclear Performance Plan
ML20153H3891988-03-30030 March 1988
Rev 19 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual
ML20196G3301988-02-24024 February 1988
Limited Test Program for Determining Axial Load Capacity of Cast One-Hole Conduit Clamps
ML20147E9511988-01-21021 January 1988
Revised, Procedures Generation Package
ML20153H3851988-01-0505 January 1988
Rev 18 to Sequoyah Nuclear Plant Offsite Dose Calculation Manual
ML20147E5691987-12-17017 December 1987
Rev 4 to Special Maint Instruction SMI-0-317-61, Instrumentation Features Walkdown,Rework & Insp Instructions for CAR 87-014
ML20237C5451987-10-28028 October 1987
Rev 17 to Offsite Dose Calculation Manual
ML20236E6931987-10-17017 October 1987
Rev 2 to Engineering Organization & Operating Procedures, TVA Employee Concerns Special Program
ML20235X0551987-10-10010 October 1987
Rev 0 to Sys Operating Instruction SOI-74.2, Removal of RHR for Repair of 2-FCV-74-2
ML20235X0651987-10-10010 October 1987
Rev 0 to Special Maint Instruction SMI-2-74-1, Repair of 2-FCV-74-2
ML20237H2051987-08-28028 August 1987
Rev 0 to Civil Engineering Branch Instruction CEB-CI 21.89, Mod Priorities for Pipe Supports on Rigorously Analyzed Category I Piping - Sequoyah Unit 2
ML20207G5821987-08-24024 August 1987
Rev 14, Balance of Plant Temp Monitoring Sys
ML20237L3651987-08-21021 August 1987
Unit 2,Regeneration of Support Design Calculations on Rigorously Analyzed Piping,Program Plan
ML20236Q1771987-08-0707 August 1987
Rev 9 to Surveillance Instruction SI-114.1, ASME Section XI Inservice Insp Program. Rev Corrects Deficiencies Shown in Caqr CH5870006 & CH5870010,adds Punchlist & Incorporates Icf 87-708
ML20236N7601987-08-0606 August 1987
Revised Radiological Emergency Plan Implementing Procedures, Including Rev 13 to IP-8, Personnel Accountability & Evaluation & Rev 6 to IP-15, Emergency Exposure Guidelines
ML20236M7181987-07-28028 July 1987
Rev 1 to WP-17-SQN, Vendor Weld Quality, Welding Project, TVA Employee Concerns Special Program
ML20236M7351987-07-24024 July 1987
Rev 5 to 80503-SQN, Document Distribution Control, Element Rept,Tva Employee Concerns Special Program
1999-06-22
[Table view] |
Text
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o o o cgis .ort=pasargypwteCONyn g::s pgggya w ,y p; l
Sequoyah Nuclear Plant DISTRIBITTION I ,
MODIFICATION AND ADDITIONS IC Plant M,.c. , rei Pwr Plant Superintendent INSTRUCTION Assistant Pwr Plant Supt. (Oper.)
10 Assistant Pwr Plant Supt. (Maint.)
Assistant Pwr Plant Supt. (H&S)
M&Al-7 Administrative Supervisor l Maintenance Supervisor (M)
ELECTRICAL PENETRATION SPLICING, IU Assistant Maintenance Supervisor (M)
CABLE SPLICING AND CABLE REPAIR IC Maintenance Supervisor (E)
INSTRUCTIONS IC Assistant Maintenance Supervisor (E)
I Maintenance Supervisor (I)
Results Supervisor Operations Supervisor IC Quality Assurance Supervisor Health Physics Supervisor Public Safety Services Supv.
Chief Storekeeper I IC Preop Test Program Coordinator Outage Director Chemical Engineer (Results)
I Radiochem I.aboratory Instrument Shop Reactor Engineer (Results)
I Instrument Engineer (Maint. I)
Mechanical Engineer (Results)
Plant Services Supervisor Training Center Coordinator I Prepared By:
Revised By:
Lynn Cowan Jan Kile Public Safety Services - SNP Shift Engineer's Office Unit Control Room I Submitted By:
/ Su'pe rvi sor IU 10 Health Physics Laboratory Nucir Document Control Unit Pwr Plant Superintendent, WBNP G
I PORC Review: _ ,,fw/ si Datd IU Pwr Plant Superintendent, BFNP Pwr Plant
- Superintendent, BENP NEB-K Resident NRC Inspector - SNP I Approved By:
a fh Pwr Plt Superintendent IC NSRS-K Technical Support Center Date Approved: Unit Control Room #2 ss/aw/#/
' ' Compliance Section Staff Supervisor IC Asst. Outage Director IU Outage Director, Watts Bar I Rev. No. _Date Revised Pages Rev. No. Date Revised Pages 0 11/8/79 All
_1 3/4/80 Revised 1,2,18,19,46, 47,48,Added 50-56 and Title Change 2
h 49,55,56 I The last page of this instruction is Number 56 '.
I 86110S0337 861031 PDR ADOCK 05000327 p PDR - -
0 0 0 3 6' SQNP
, "' N C
f ng H&AI-7 I
., Page 4 of 19 Rev. 0 6.0 PHOCEDUHE (Cont.)
A. (Cont.)
Either noninsulated or self-insulated butt splices may be installed in systems of 600V or less and wire size No. 10 AWG and smaller. Self-I innulated butt splices within the primary containment shall be either Terzel (Thomas and Betts Company) or Kynar (AMP Special Industries). The vinyl or nylon self-insulated fittings are intended for applications where the total temperature of the conductor does not exceed 105'c (221'F).
I Splices of 600V or less, wire size No. 8 AWG and larger, and those of the noninsulated type for smaller wires shall be insulated with Ray-I chem Corporation WCSF-N splice covers and installed in accordance with the manufacturer's instructions using an electric heat gun (do not use torch with open flame) available from Raychem as the heat source.
Unless otherwise noted on design drawings, rahles with rubber or rubber-like (nalicone) 125*C or a; ore insulation, in systems of 600V or less, shall be spliced by one of the following procedures:
- a. Install r.oninsulated butt splice of appropriate size and build up over exposed copper surfaces with 3M Company, Scotch 70 tape (temp-I crature rating of 180*C) to a thickness equal to the original in-sulation. The use of Raychem's WCSF-N shall be used as a replace-ment for the Jacket material,
- b. For splices in multiple-conductor cable, splice and insulate the single conductors in accordance with a. above. The use of Ray-chem's WCSF-N (section 2.2.3) shall be used as a replacement for I the Jacket material for the overall Jacket, and shall be installed as shown in Attaciunent 2.
Install self-insulated butt splices for wire size No.10 AWG and I' r.
nmaller. Self-insulated butt splices shall be either Tefzel or Kynar. Thenc self-insulated butt splices are intended for ap-piirations where the total Lcmperature of the coaductor does not exceed IS0*C (300*F), e.g., within primary containment.
The following list serves as a guide only to the splice types (attached) for the various penetrations:
I I
l I
- j. - .-
.a g,g'
' ' p.,.,, , ;u. .
0 0 0 3*.6 2 l . ] 0, 4 3.g
~ Sequoyah Nuclear Plant Review Transmittal '
Infor:::a1 PORC Review n=tr2ct:ca ..c. Mr.AT-7 ELECTRICAL P EETRATION SPLICING, 7.evtston io. 7 Title cARTT 5:Pf.TCTNC AND CARTT RFPATR INSTRUCTIONS Review n:ct ne :ompicteo in the time indicated. Attaen ecceente by marking up the instruction or attacning additional cheets. The orttinator of each corament should be identtiicd b/ his initials.
FLZ.\SE ~0:!?LETF. TOCR REVIEW IN 'iORKING DAYS
- . Occrations Suoervisor: Date Reviewed /B /7[dl Signed /
j :. M::n unanca 5 :pervisor (?!): Date Reviewed /pdeh'r Si:;ned JP//* ! _,
- f. '!atntenance :;u;)crvthor (E): Date Reviewed tolulet Signed k
'fa nt nance .:u nearvisor t.I): Date Reviewed e nA Signed ' pdm
.. .'*ea l th Phve. :<:: .it : Date Reviewed /0 L Signed
,. '.:1 ity .t u.u r a nc.: Sunervssor: Date Revtewed _ f e/,a >// Signed fr/ h 7 .te w l :. : ::nne rv i :o r : Date McViewed fo/ M/gr Signed ,A
- 1. :.s ie r.v in:n nee r: Date Reviewed $hI Signed A)/A
- i. /icatstmt Plant :fanager: 3. ate Reviewco Signed /
- 10. ?lant ta n::; :r: Date Reviewed /6-84-8/ Signed /I[d/
~
11.
. *y
.. ..o.r*...m .
~
s .g - es -. . u..
to re:oive PORC comments'.and return to PLANT
/
ORIGINATING SUPERVISOR DATE
!2. ?*.ld;T !??. VICES tor incorporating cocnents. r///- / // J Initials - Cat
...............................................____...............e ......
- 13. tibr / to revtew finst copy for FORMAL PORC.
- W'O (IGisATING SUPERVISOR i/Ho-81DATE l '. . ?L.'.:iT ';;;3V!CP.S coversheet verification. M /_// .7() //
Initials '
D/ -
.............__.........................................................te .........
P.EAECN FOR .E V!S:0N. (Checx appropriate reason (s) ar.d clarify reason in remarits)
- 1. Change in ? cility Design.
- 2. Change in Tech Suces or performance characteristics.
- 3. C: ant:r ta c::urove datety of operation.
I. . Change to clartf r, correct, expan<s. or simplify procedure.
- 5. Other, aptain in ecmarxs.
REMARKS: Add place for workplan number or MR number.
. ri
. . . m. -
. . - - .. .. ... =_- - 2 --" %.'::+'t&.
'-~% .
P O O362 l 3Q7 -
Standard Practice -
Page 2 .
SQA119 Attachment 1 3/19/81 f A. D
/Yes ription of Change (Include TACF, Instruction or STEAR Number) 4-z a,rbcog/sv um}dsr , mamle su n1P mods s AWAT 'i ---
g B. (1) Is the facility or instruction being changed described in the Safety g Analysts Report? Yes / No NA (2) Is the test, experiment or activity described in the Safety Analysis
, Report? Yes No t/ NA If the answer to (1) is yes or (2) is no, then complete Sec ion C.
llAf) /0
'~
/
ignature/Date' C. Unreviewed Safety Question Determination L* (1) Is the probability of an occurrence or the consequences of'an acci-dent or malfunction of equipment important to safety previously j evaluated in the Safety Analysts Report increased? Yes No /
I Ex 1anation d}un twe 5n.Lo lo dbutNAidbru adl@6Y1/bdk nariL _
Dat' bt Arn6m r%&rJh.
N @rn/ at/;uv/t b 1a 6 & s/ i Niunnt. m/JNAu t
d rof nede ou t/L ./2m,> De// n f A iersu i (2) Is the possibility for an accident or malfunction of a different type
( than evaluated previously in the Safety Analysis. Report created?
Yes No /
Exp)anation dw_ Art,v. u),,n ah42sf6ua$ o dNA/xb$Jo-t ACtl&ftx8 6tAmt/ J' ku??dn> f)ur u 'mo uurne/L h n /.f'a AJ_ /
f (3)~ Is the margin of safety as defined in the basis of any technical specification reduced? Yes No / -
Explanation h andD7bNs (b /1st
- s. b' w Alt. @ ney n , c/
l
/ ~d' (
A)$11/
ftb/1MfArnkteti -
' /0 '
iP/
/ Signature /Datd D. PORC concurs with the above evaluation. a_.srt n/as/&
PORC Chairman /Date' f E. Pl. ANT SUPERINTENDENT concurs with the ab'ove evaluation.
g' WW Plant Superintendent
_
