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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 ML20078P8251995-02-10010 February 1995 Proposed Tech Specs 2.10 to Relocate Requirements for Incore Instrumentation Sys ML20077S1691995-01-0909 January 1995 Proposed Tech Specs,Reflecting Deletion of Requirements for Toxic Gas Monitoring Sys ML20078G8981994-11-11011 November 1994 Proposed Tech Specs 5.2 & 5.5,reflecting Administrative Changes ML20024J3921994-10-0707 October 1994 Proposed Tech Specs,Deleting SRs in TS 3.6(3)a for Eight Raw Water Backup Valves to Containment Cooling Coils,Deleting SRs in TS 3.2,Table 3-5,item 6 for 58 Raw Water Valves & Revising Basis of TS 2.4 to Reflect Changes ML20069H9261994-06-0606 June 1994 Proposed Tech Specs Incorporating Changes to Credit Leak Before Break Methodology to Resolve USI A-2, Asymmetrical Blowdown Loads on Rcps ML20069D8451994-05-25025 May 1994 Proposed Tech Specs Requesting one-time Schedular Exemption from 10CFR50.36a(2) ML20062N4211993-12-28028 December 1993 Proposed TS Tables 3-1 & 3-2 Re Min Frequencies for Checks, Calibrs & Testing of RPS & Min Frequencies for Checks, Calibrs & Testing of ESFs & Instrumentation & Controls, Respectively LIC-93-0228, Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys1993-08-20020 August 1993 Proposed Tech Specs Incorporating Changes to Leak Before Break Methodology to Resolve Unresolved Safety Issue A-2, Asymmetrical Blowdown Loads on Reactor Primary Coolant Sys ML20045H1791993-07-12012 July 1993 Proposed TS 2.14,Table 2-1,Item 6.b Re ESF Sys Initiation, Degraded Voltage Setting Limits LIC-93-0159, Proposed Tech Specs Incorporating Administrative Changes1993-06-17017 June 1993 Proposed Tech Specs Incorporating Administrative Changes ML20128E5341993-02-0808 February 1993 Proposed Tech Specs Deleting Section 5.9.4 Re Radioactive Effluent Release Rept.Draft Chemistry Manual Procedure Encl ML20128C0461993-02-0101 February 1993 Proposed TS Figures 2-1A & 2-1B Re pressure-temp Limits for Heatup & Cooldown,Respectively 1999-05-26
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195B4441999-05-26026 May 1999 Proposed Tech Specs Relocating pressure-temp Curves, Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS pressure-temp Limits Rept ML20205J7671999-03-31031 March 1999 Proposed Tech Specs Increasing Min Required RCS Flow Rate & Changing SRs for RCS Flow Rate LIC-99-0001, Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR1999-01-29029 January 1999 Proposed Tech Specs Relocating Three cycle-specific Parameter Limits from FCS TS to COLR LIC-98-0141, SG Eddy Current Test Rept for 1998 Refueling Outage. with1998-10-27027 October 1998 SG Eddy Current Test Rept for 1998 Refueling Outage. with ML20151U3871998-09-0404 September 1998 Revised Bases of TS Sections 1.3(8),2.0.1(2),2.1.6,2.3,2.4, 2.13,2.15,3.1 & 3.6 ML20217B8611998-03-18018 March 1998 Proposed Tech Specs 5.2 & 5.11.2,changing Title of Shift Supervisor to Shift Manager ML20217B8241998-03-18018 March 1998 Proposed Tech Specs Re Requirements for Alternate Shutdown Panel & Associated Auxiliary Feedwater Panel ML20217P2041998-03-0303 March 1998 Proposed Tech Specs Pages,Revising TS 2.6 & Basis by Replacing Refs to TS 3.5(4) W/Refs to TS 5.19 ML20199L7291998-01-30030 January 1998 Proposed Tech Specs Deleting Section 3.E Re License Term ML20199L8951998-01-30030 January 1998 Proposed Tech Specs,Reflecting Relocation of pressure-temp Curves,Predicted Radiation Induced NDTT Shift Curve & LTOP Limits to FCS Unit 1 RCS PT Limits Rept ML20202B0931998-01-30030 January 1998 Proposed Tech Specs Section 2.5 Re Steam & Feedwater Sys ML20203G4311997-12-11011 December 1997 Proposed Tech Specs,Adding New LCO to TS 2.15 Pertaining to Inoperable ESF Logic Subsystem ML20199K1391997-11-21021 November 1997 Proposed Tech Specs 5.19 Re Containment Leakage Rate Testing Program ML20217G4601997-10-0303 October 1997 Proposed Tech Specs Pages Revising TS Surveillance 3.9, Auxiliary Feedwater Sys, to Clarify What Flow Paths Are Required to Be Tested & Delete Specific Discharge Pressure ML20211N7591997-10-0202 October 1997 Rev 0 to Fort Calhoun Station Unit 1 Operating Instruction, OI-ES-3, Engineered Safeguard Controls Normal Mode 1,2 & 3 Alignment Check ML20211N7521997-09-21021 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-04, Annunciator Marking ML20211N7471997-09-12012 September 1997 Rev 2 to Fort Calhoun Operations Dept Policy & Directive OPD-6-08, Plastic Label Usage ML20211N7661997-08-25025 August 1997 Rev 4 to Fort Calhoun Station Unit 1 Annunciator Response Procedure ARP-1, APR-1 Annunciator Response Procedure ML20211N7411997-08-24024 August 1997 Rev 0 to Fort Calhoun Operations Dept Policy & Directive OPD-5-14, Test Monitor Program ML20196J0851997-07-25025 July 1997 Proposed Tech Specs Implementing Option B of 10CFR50,App J & Allowing Frequency of Conducting ILRT & Local Leak Rate Testing to Be Based on Component Performance ML20137Y1801997-04-17017 April 1997 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20137H4941997-03-26026 March 1997 Proposed Tech Specs Incorporating Addl Restrictions on Operation of MSSVs ML20138L4361997-02-20020 February 1997 Proposed Tech Specs 5.0 Re Administrative Controls ML20134J6841997-01-20020 January 1997 Rev 5,Change a to Security Training & Qualification Program LIC-96-0183, Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents1996-11-20020 November 1996 Proposed Tech Specs 5.0 Re Administrative Controls & Table of Contents ML20129E5161996-10-24024 October 1996 Proposed Tech Specs 4.3.2,regarding Reactor Core & Control to Allow Use of Either Zircaloy or ZIRLO Cladding Proposed Additional Reference to Westinghouse Topical Report, WCAP-12610-P-A, Vantage + Fuel Assembly Rept ML20129C2621996-10-22022 October 1996 Proposed Tech Specs 5.0 Re Administrative Controls & 5.9.5 Re Core Operating Limits Rept LIC-96-0125, Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core1996-08-23023 August 1996 Proposed Tech Specs Revising Paragraph 2.B(2) of License to Allow Use of Source Matl as Reactor Fuel.Ts 4.3.2 Revision Would Include Depleted U in Describing Reactor Core ML20115G0041996-07-15015 July 1996 Proposed Tech Specs 4.3.2 Re Reactor Core & Control ML20112D3211996-05-31031 May 1996 Proposed Tech Specs Re LCO for Trisodium Phosphate & Increasing Min Required Amount of Trisodium Phosphate Contained in Containment Sump Mesh Baskets ML20117H6981996-05-20020 May 1996 Proposed Tech Specs,Clarifying Surveillance Test Requirements Found in TS 3-1,Tables 3-1,3-2,3-3 & 3-3A ML20117H5931996-05-17017 May 1996 Proposed Tech Specs,Relocating Operability Requirements for Shock Suppressors (Snubbers) to USAR & or Plant Procedures & Incorporating Snubber Exam & Testing Requirements Into TS 3.3 ML20129C5351996-03-0101 March 1996 Rev 0 to Incore Instrumentation Operability Requirements ML20097C3081996-02-0101 February 1996 Proposed Tech Specs,Allowing Increase in Initial Nominal U-235 Enrichment Limit of Fuel Assemblies That May Be Stored in Spent Fuel Pool LIC-96-0008, Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition1996-01-22022 January 1996 Proposed Tech Specs Placing Sirw Tank Low Level Channels in Bypass Rather than Tripped Condition ML20108A7161995-12-19019 December 1995 Rev 7 to CH-ODCM-0001, ODCM, Incorporating TS Amend 171 for Section 3.1 Update/Reflect Changing Environ ML20094N8631995-11-16016 November 1995 Proposed Tech Specs,Adding LCO & Surveillance Test for Safety Related Inverters & Deleting Nonsafety Related Instrument Buses ML20092G0771995-09-0606 September 1995 Proposed Tech Spec 2.7,extending Allowed Outage Time from 7 Days Per Month to 7 Days W/ Addl Once Per Cycle 10 Day Allowed Outage Time ML20091P4011995-09-0101 September 1995 Rev 3 to Fort Calhoun Station ISI Program Plan Third Ten-Yr Interval 1993-2003 ML20087E0281995-08-0404 August 1995 Proposed Tech Specs Reducing Minimum Operable Containment Radiation High Signal Channels ML20086D5341995-06-27027 June 1995 Proposed Tech Specs Re Reformation & Clarification of TS Re Chemical & Vol Control Sys ML20091G3601995-06-26026 June 1995 Proposed Tech Specs Re Extension of Allowed Outage Time for an Inoperable Low Pressure SI Pump ML20086D3851995-06-26026 June 1995 Proposed Tech Specs Re Audit Frequencies for Plant QA Program ML20085M0081995-06-15015 June 1995 Rev 2 to ISI Program Plan for 1993-2003 Interval ML20084G7751995-05-31031 May 1995 Proposed Tech Specs,Requesting Amend to Provide Addl Restrictions on Operation of CCW Sys Heat Exchangers ML20083C0091995-05-0808 May 1995 Proposed Tech Specs,Incorporating Proposed Revs Per GL 93-05 to Specs 2.3,3.1,3.2,3.3 & 3.6 ML20087G9691995-04-0707 April 1995 Proposed Tech Specs Re Relocation of Axial Power Distribution Figure for License DPR-40 ML20082J0851995-04-0707 April 1995 Proposed Tech Specs Re Administrative Changes to License DPR-40 ML20108A7121995-03-15015 March 1995 Rev 6 to CH-ODCM-0001, ODCM, Incorporating New TS Amend 164 ML20080S0291995-03-0101 March 1995 Proposed Tech Specs Reflecting Administrative Revs to TS 5.5 & 5.8,per GL 93-07 & Revs Unrelated to GL 93-07 to TS 2.5, 2.8,2.11,3.2 & 3.10 1999-05-26
[Table view] |
Text
_ _ _ _ _ _ _ _ _ .
o 50 ADMT? T3"'RATI'*E CN!TRn!S 5.h Trsininn 5.4.1 A retrainine, and replace..ent training proccan for the plant staff shall be naintainea under the directi:n of the Cupervisor - Ctation Training and shall r.eet er ex:ced the requirer.ent: cf Tecticn 5.5 -f A::3I ':18.1 1971 and Appendi:: A of 10 C:~3 Fart 55.
5.a.C A traininn procran f:r the rire bricade chall be maintaine: uncer the
- '.anscer - Fort Calbran f tatia. and chall reet er execel the require ents of Ce:ti;n 07 of ::TPA Ccde-? Air. ex:ept that the eetina frecuency .sv it quarter 1'. / ,
5.5 Per!ev ans Au11t
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, %nett n 55.1.1 "'t.e Tiant T w uv rr.ittee Onall functicn t0 advice the "2 nager - fort C21hoan Statica cn all .atter; related to nu: lear afety.
J'e-rc e t t ic n 5.51.0 The cfficial fin.; Review C=r.it. tee ensil be cenpcsed er the t Chairman: !!anacer - Tort Calhoun Ctation
~~ ~ x 4 te .be r : Superviser - Cperat.icns d "enter: Cupervi:Or - Technical X "enter: h rervisor - Maintenance _ _ ____. _ _ _ __. _
vag i - _ H5f? t?e_e--- not Gi daC._E_rtJL.+ m46 . - d _
"ed er: Fes:t:r Engineer Member: Supervisor - Chemistr'/ and Radiati:n Prctection Meneert Flant Engineer ,
g , y l h u c. o mem be r- t dure r v e ff r - t .l ch i c s (v~g.m bc e . Lguvs%Dr - T. C C-
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Alt ernat es
- 5. 5.1. 3 Alternate nesbers chall be appoint *d in vriting by'the Pl. ant Review Cotrtittee Chair .an to serve on a temporary basin, however, no more than two alternates shall participate in Plant Reviev Con ittee activities at any cne time, teetine Frewency
- 5. 5.1. . The Flant Review C:nnittee shall meet at le4.st cnce per calendar nontn and as convened by the Plant Review Cc:.mittee Chairr.an.
1 Quorum 5.5.1 5 A qucrun of the Plant Review Comittee shall censist of the Chaiman and four ::.ecers int:luding alternates.
8803150272 080309 ! 5-3 Amendment No. 9, 17, 38, 814 PDR ADOCK 05000265 P nr n *
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5.0 ADMINISTRATIVECONTROLS_
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1 g 5.5.1.7 b. Render determinationt (n writing with regard to wether hr not each item considered unoer 5.5.i'.6(a) through (e) above constitutes an unreviewed safety g hstion.
- c. Provide imediate wr'tten potification to fte Divi-ion Manager -
Nuclear Production and'Se Safety Audit and 9eviwlorsittee of ,
disagreement between tne Plant Review Comittee and the Manager - , ,
Fort Calhoun Station;-r.owever, the Manager - ForQCalhoun Station "
shall have responsibiHty for resolution of such t'isagreements j pursuant to 5.1.1 abcVe. - j Records 'I
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5.5.1.8 The Plant Review Comittee shall maintain written :ninutes of 'each meeting and copies shall be provMed to the , Division Manager ' HEMar :
Production and Chairman of the uff r.*/ Audit and. QAv 4 - ,
Comittee. ,
5.5.2 Safety Audit and Review Comittee (SAF,gj.
, \
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Function s s ,
5.5.2.1 The Safety Audit and Review Co.nittes shall fundOEri to provide the independent review and audit of designet.ad activiuh in the areas of:
nuclear power plant operation
- a.
- b. nuclear engineering y ;
- c. chemistry and radiochemistry '
- d. metallurgy N ')
- e. instrumentation and control i '
radiological safety J '
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f.
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- g. mechanical and electrical engipaering -
- h. quality assurance , ,i
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4 5.5.2.2 The Safety Audit and Review Comittee shdl be composed of: 1 d
,s ) i Chairman: Division Manager - Quality Ahiurance and ilegulattyh /.Wirs ;
Member: Senior Vice President J rod'.dtt on l 3-1 Operations Fnl:, M W Necieer tk R u do3roduction,M@ #CP ~
Wh,1g' "
Member:
Member:
Vice President - Engineerino and Genu {in Services Division Manager - Engineerinq '
N dA p"O Member: Division Manager - Nuclear Pr'othetici ;A Member: OPPD Operations, Engineedng, Md Technicai 'ifrport staff '
7 Member: Qualified Non-District Mfiliated Consultants as Required and as Determined by SARC Chairman l
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3 E l 5-5 Amendment No. 9.J9,H ,75,86,93,99,101 )
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, 5.0 ADMINIS1 NATIVE CONTROLS 5.5,2.8 e. . Thelf ort Calhoun Station Emergency Plan and implementing procedures j j at, led t once every twelve months.
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- f. lhe Site Security Plan and imolementing procedures at least once every twelve months, i
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- g. The Safeguards Contingency Plan and implementing procedures at
, .J 3 \ least once every twelve months.
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' \ ,, h. The Radiological Effluent Program including the Radiological Environ-
^
< mental Monitoring Program and the results thereof, the Of fsite Duse i i
Calculation Manual and ipplementing procedures, and the Process i Control Program for the solidification of radioactive wastes at least once per 2 years. ;
- i. Any other area of facility operation considered appropriate by the i 1 Safety Audit and Review Comittee or the Senior Vice President - I Huclear Production, Production Operations, fueh, ad Quality i
Assurancg 4-Regulegry-Affe4rs, .td /hhanat, $1 _vur7 Autrority E.5.2.9 Ine Safety Audit and Review Comittee shall report to and advise the Senior V;ce President - Nucleargraduction, Production Operations,-Fue4A l l
=aad-luolity Assuranc '
requistory-Af4+4esan those areas of responsi-bility specified in tions 5.5.2.7 and 5.5.2.8. . ;
Records a
d.5.2.10 Records of Safety Audit and Review Co'rtunit, tee activities shall be prepared, '
approved and distributed as indicated btiow:
- a. Minutes of each Safety Audit and Review Committee meeting shall be prepared, approved and fomarded to the Senior Vice President - I Nuclear Productiegg Production Operations, Mist-c.d Quality Assurance MR / hl=h= L'Telzs within En14 Wda s. following each meeting.
-I
- b. Reports of reviews encompassed by Section 5.5.2.7e, f, 9. h. and i
(
above shall be prep 2 red, approved and fomarded to the Senior Vice i President - Nuclear Produ ion, Production Operations. ,"ueh , cr.d-Quality Assuranceq&-Regula eey-Af444rs within 14 days following completion of the rirvrew. s amd.
- c. Audit reports encompassed by Section 5.5.2.8 above shall be forwarded to the Senior Vice President - Nuclear Production, Production Opera- i twions yeth and Quality Assurance & Regulatory Affairs and to the I - Fesponsible management Review Comittee withinpositions designated 30 days after by the completion of Safety Audit and the audit.
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A ** OTHER VICE-PRESIDENT POSITIONS EXIST WHICH HAVE NO DIRECT INVOLVEMENT WITil FACILITY I4ArJAGEf1Er1I OR TEClirJICAL SUPPORI.
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