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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217K9761999-10-14014 October 1999 Amend 234 to License DPR-56,changing TS in Response to 990301 Application & Suppls ,1001 & 06,to Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Monitoring Sys ML20217B4261999-10-0505 October 1999 Amend 233 to License DPR-56,changing Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Repts ML20216H6891999-09-24024 September 1999 Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively, Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by TSs SR 3.9.1.1 ML20211D5471999-08-23023 August 1999 Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Correct Typo & Editorial Errors Introduced in TSs by Previous Amends ML20205K7371999-04-0707 April 1999 Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively, Consisting of Changes to TS SRs Re Secondary Containment Doors in Response to 980204 Application,As Revised by ML20155C6011998-10-26026 October 1998 Amend 226 to License DPR-44,revising TSs for Safety Limit MCPR from Current Value of 1.11 to 1.10 for Two Recirculation Loop Operation & from 1.13 to 1.12 for Single Recirculation Loop Operation ML20154J2261998-10-0505 October 1998 Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Delete Requirements for Functional Testing of SRVs During Each Unit Startup ML20154H4691998-10-0505 October 1998 Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Permit Incorporation of EOC-RPT Sys at Plant,Units 2 & 3 ML20154G6551998-10-0101 October 1998 Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively, Revising Plant,Units 2 & 3 TSs to Exclude MSIV Leakage from Total Type B & Type C Local Leak Rate Test Results ML20153B9581998-09-14014 September 1998 Amend 9 to License DPR-12,adding Requirements for Control of Effluents & Annual Reporting Per 10CFR50.36a ML20238F2611998-08-24024 August 1998 Amend 222 to License DPR-44,revising Pbaps,Unit 2 TSs to Support Mod P00271,which Would Replace SRMs & IRMs W/Wrnms, During Forthcoming Outage 2R12,scheduled for Early Oct 1998 ML20212G8261997-10-24024 October 1997 Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively, Changing TSs to Eliminate Inconsistency Between ECCS Operability Requirements & Autostart & Protective Trip Bypass of EDGs on ECCS Initiation Signal ML20217J5571997-10-0909 October 1997 Amend 225 to License DPR-56,revising MCPR Safety Limit in Section 2.1 of TSs from 1.07 to 1.11 for Two Recirculation Loops in Operation ML20217D8101997-09-30030 September 1997 Amend 224 to License DPR-56,revises TS to Support PBAPS Mod P00271,which Would Replace Source Range & Intermediate Range Monitors W/Wide Range Neutron Monitoring System ML20216G5321997-09-0404 September 1997 Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively, Revising TS to Extend Replacement Frequency for Inflatable Seat Seals for Primary Containment Purge & Vent Valves to 96 Months ML20217M7961997-08-19019 August 1997 Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively, Extending APRM Flow Bias Instrumentation Surveillance Interval from 18 Months to 24 Months ML20135B3851997-02-19019 February 1997 Amends 218 & 221 to Licenses DPR-44 & DPR-56,respectively, Changing Min Allowable Charging Water Header Pressure from Value 955 Psig to Value of 940 Psig in TS 3.10.8 ML20062C0401978-10-16016 October 1978 Amend 48 to License DPR-44,revising Tech Specs to Permit Plant Operation W/New 8x8R Reload Fuel for Cycle 4 ML20062B0551978-10-10010 October 1978 Amend 47 to License DPR-56,changing Tech Specs Re Fire Protection & Administrative Controls ML20062B0521978-10-10010 October 1978 Amend 47 to License DPR-44,changing Tech Specs Re Instrumentation That Initiates or Controls Core & Containment Cooling Sys,Administrative Controls & safety-related Snubbers ML20062B8621978-10-0303 October 1978 Amend 46 to License DPR56,changing Tech Specs Re Surveillance of Suppression Pool Temp Logging,Controlled Bypass Heatup Line on HPCI Steam Supply & Identification of Valves to Reflect Plant Unique Designation ML20062B8481978-10-0303 October 1978 Amend 46 to License DPR-44,changing Tech Specs Re Surveillance of Suppression Pool Temp Logging,Controlled Bypass Heatup Line on HPCI Steam Supply & Identification of Valves to Reflect Plant Unique Designation ML20210Q3391973-10-25025 October 1973 Amend 1 to License DPR-44 & Amend to License DPR-56, Reflecting Change in Corporate Structure at Pse&G 1999-09-24
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217K9761999-10-14014 October 1999 Amend 234 to License DPR-56,changing TS in Response to 990301 Application & Suppls ,1001 & 06,to Support PBAPS Mod P00507,which Will Install Digital Pr Neutron Monitoring Sys ML20217B4261999-10-0505 October 1999 Amend 233 to License DPR-56,changing Minimum Critical Power Ratio Safety Limit & Approved Methodologies Referenced in Core Operating Limits Repts ML20212H5071999-09-27027 September 1999 Application for Amends to Licenses DPR-44 & DPR-56,change Application ECR 96-01511,to Revise TS Re Loss of Power Setpoints for 4 Kv Emergency Buses ML20216H6891999-09-24024 September 1999 Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively, Delete SR Associated Only with Refueling Platform Fuel Grapple Fully Retracted Position Interlock Input,Currently Required by TSs SR 3.9.1.1 ML20211M7081999-09-0101 September 1999 Suppl License Change Application ECR 99-01497 for Licenses DPR-44 & DPR-56,correcting Minor Discrepancies Discovered in Pages of Attachment 2 ML20211D5471999-08-23023 August 1999 Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Correct Typo & Editorial Errors Introduced in TSs by Previous Amends ML20210P8811999-08-11011 August 1999 Application for Amends to Licenses DPR-44 & DPR-56 in Order to Clarify PBAPS Licensing Basis to Include Specific Info Re Allowed Containment Overpressure Credit Needed to Ensure Adequate NPSH Available for ECCS Pumps.Ufsar Changes,Encl ML20210N0711999-08-0606 August 1999 Exigent License Change Application ECR 99-01727 for Licenses DPR-44 & DPR-56,incorporating Note Into TS Which Will Permit one-time Exemption Until 990930,from 90 F Limit Stated in SR 3.7.2.2 ML20209F7641999-07-12012 July 1999 License Change Application ECR 99-01255,revising TS Sections 2.1.1.2 & 5.6.5 by Incorporating Revised SLMCPR & Deleting Previously Added footnotes.Non-proprietary & Proprietary Info Re Slmcpr,Encl.Proprietary Info Withheld ML20209B9141999-07-0101 July 1999 Application ECR 99-01497 for Amend to Licenses DPR-44 & DPR-56,reflecting Change in Corporate Structure ML20205K7371999-04-0707 April 1999 Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively, Consisting of Changes to TS SRs Re Secondary Containment Doors in Response to 980204 Application,As Revised by ML20205F6221999-03-29029 March 1999 Application for Amends to Licenses DPR-44 & DPR-56,revising TS to Delete Requirement for Refuel Platform Fuel Grapple Fully Retracted Position Interlock Currently Required by TS Surveillance Requirement 3.9.1.1 ML20207E2421999-03-0101 March 1999 License Amend Request ECR 98-01802 for Licenses DPR-44 & DPR-56,proposing Changes to Support PBAPS Mod P00507 Which Will Install Digital Power Range Neutron Monitoring Sys & Incorporate long-term T/H Stability Solution Hardware ML20198N2471998-12-24024 December 1998 License Change Application ECR 96-01511,revising Setpoints & Limits of Allowable Values for LOP Instrumentation for 4kV Emergency Buses Contained in TS Table 3.3.8.1-1, LOP Instrumentation ML20155C6011998-10-26026 October 1998 Amend 226 to License DPR-44,revising TSs for Safety Limit MCPR from Current Value of 1.11 to 1.10 for Two Recirculation Loop Operation & from 1.13 to 1.12 for Single Recirculation Loop Operation ML20154H4691998-10-0505 October 1998 Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Permit Incorporation of EOC-RPT Sys at Plant,Units 2 & 3 ML20154J2261998-10-0505 October 1998 Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively, Revising TSs to Delete Requirements for Functional Testing of SRVs During Each Unit Startup ML20154G6551998-10-0101 October 1998 Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively, Revising Plant,Units 2 & 3 TSs to Exclude MSIV Leakage from Total Type B & Type C Local Leak Rate Test Results ML20153B9581998-09-14014 September 1998 Amend 9 to License DPR-12,adding Requirements for Control of Effluents & Annual Reporting Per 10CFR50.36a ML20238F2611998-08-24024 August 1998 Amend 222 to License DPR-44,revising Pbaps,Unit 2 TSs to Support Mod P00271,which Would Replace SRMs & IRMs W/Wrnms, During Forthcoming Outage 2R12,scheduled for Early Oct 1998 ML20236R3011998-07-10010 July 1998 Application for License Change ECR 98-01403,requesting Change to License DPR-44 Revising TS Section 2.0 & non-proprietary & Proprietary Versions of 980609 Addl Info Re 1.10 Cycle Specific Slmcpr.Proprietary Version Withheld ML20247C2481998-05-0101 May 1998 License Change Application ECR 98-00499 for Amends to Licenses DPR-44 & DPR-56,revising TS to Delete Requirements for Functional Testing of SRVs During Each Unit Startup ML20217G7481998-03-20020 March 1998 License Change Application ECR 97-02809,revising Tech Specs to Incorporate end-of-cycle Recirculation Pump Trip Sys at Units 1 & 2 ML20217Q4631998-03-0202 March 1998 Application for Amend to License DPR-12,adding Requirements to TS to Achieve Compliance w/10CFR50.36a, TS on Effluents from Nuclear Power Reactors ML20202F4151998-02-0404 February 1998 Application for Amends to Licenses DPR-44 & DPR-56,revising SR 3.6.4.1.2 & Associated Bases to Reflect Changes in Requirements for Secondary Containment Doors ML20212G8261997-10-24024 October 1997 Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively, Changing TSs to Eliminate Inconsistency Between ECCS Operability Requirements & Autostart & Protective Trip Bypass of EDGs on ECCS Initiation Signal ML20217J5571997-10-0909 October 1997 Amend 225 to License DPR-56,revising MCPR Safety Limit in Section 2.1 of TSs from 1.07 to 1.11 for Two Recirculation Loops in Operation ML20217D8101997-09-30030 September 1997 Amend 224 to License DPR-56,revises TS to Support PBAPS Mod P00271,which Would Replace Source Range & Intermediate Range Monitors W/Wide Range Neutron Monitoring System ML20211H9171997-09-26026 September 1997 Application for Amend to License DPR-56,deleting Submitted Page 2.0-1 to Be Replaced W/Encl Page 2.0-1 & Adding Page 5.0-21 for Unit 3 ML20216G5321997-09-0404 September 1997 Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively, Revising TS to Extend Replacement Frequency for Inflatable Seat Seals for Primary Containment Purge & Vent Valves to 96 Months ML20217M7961997-08-19019 August 1997 Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively, Extending APRM Flow Bias Instrumentation Surveillance Interval from 18 Months to 24 Months ML20141G4821997-06-30030 June 1997 License Change Request ECR 96-03620,revising TS Section 2.0, Safety Limits to Incorporate Revised SLMCPRs Due to Use of GE13 Fuel Product Line & cycle-specific Analysis Performed by GE ML20140D8501997-06-0404 June 1997 License Change Application ECR 97-00086,revising TS Section 3.8.2.1 to Eliminate Inconsistency Between Requirements for ECCS Operability & auto-start & Trip Bypass of EDGs on ECCS Initiation During Listed Events ML20141L0081997-05-23023 May 1997 License Change Application ECR 96-02324,revising Section 5.5.12 to Exclude Measured Main Steam Isolation Valves Leakage from Total Type B & C Local Leak Rate Test Results ML20141E0721997-05-0909 May 1997 License Change Application ECR 96-00982,revising TS SR 3.6.1.3.16 Re Replacement Frequency of Primary Containment Purge & Exhaust Valve Inflatable Seals ML20141A7861997-05-0505 May 1997 Application for Amend to Licenses DPR-44 & DPR-56,requesting Approval for Implementation of Plant Mod to ECCS Pumps in Order to Satisfy Recommendations Stipulated in NRC Bulletin 96-003 ML18102B0071997-04-30030 April 1997 Application for Amends to Licenses DPR-40,DPR-56,DPR-70 & DPR-75,requesting Consent of NRC for Indirect Transfer of Control of Interest in Plants That Will Occur Under Proposed Merger ML20137P7511997-03-31031 March 1997 License Change Request ECR 96-00627,extending Surveillance Interval for Calibr of Average Power Range Monitor Flow Bias Instrumentation from 18 Months to 24 Months ML20135B3851997-02-19019 February 1997 Amends 218 & 221 to Licenses DPR-44 & DPR-56,respectively, Changing Min Allowable Charging Water Header Pressure from Value 955 Psig to Value of 940 Psig in TS 3.10.8 ML20134F6091996-10-30030 October 1996 Application for Amend to License DPR-56,revising Slmcprs,Ts Section 2.0,by Incorporating Rev Due to GE Determination That Previous Calculation Is non-conservative ML20117L2821996-09-0606 September 1996 Application for Amends to Licenses DPR-44 & DPR-56 Adding Notes to Allow Core Spray & LPCI Pumps to Start out-of- Sequence Under Certain Conditions & Adding Notes to Selected Surveillance Requirements ML20117F9321996-08-27027 August 1996 Application for Amends to Licenses DPR-44 & DPR-56, Correcting Administrative Error in TS Re CRD Charging Water Header Pressure for Shutdown Margin Test ML20117H6711996-08-23023 August 1996 License Change Request 96-01 to Licenses DPR-44 & DPR-56, Revising TS Section 2.0, Safety Limits to Incorporate New Safety Limit Min Critical Power Ratios,Due to Use of GE13 Fuel Product Line ML20117M6981996-06-13013 June 1996 License Change Request ECR 96-02011 to License DPR-44, Permitting One Time Performance of SR 3.3.1.1.12 for APRM Flow Biased High Scram Function,W/Delayed Entry Into Associated TS Conditions & Required Actions for Up to Six H ML20101K7961996-03-25025 March 1996 License Change Request 96-01 to Licenses DPR-44 & DPR-56, Revising TS Section 2.0, Safety Limits ML20100J7361996-02-15015 February 1996 License Change Request 95-11 to Licenses DPR-44 & DPR-56, Reflecting Implementation of 10CFR50,App J,Option B ML20095J1251995-12-21021 December 1995 TS Change Request 95-08,eliminating Outdated Matl from FOLs & Making FOL for Unit 2 Consistent W/Fol for Unit 3 ML20095J6971995-12-19019 December 1995 TS Change Request 95-13 to Licenses DPR-44 & DPR-56, Correcting Administrative Error in Improved Tech Specs Re Ventilation Filter Testing Program ML20095A1621995-11-30030 November 1995 Application for Amends to Licenses DPR-44 & DPR-56, Consisting of Change Request 95-12,changing Minimum Allowable Control Rod Scram Accumulator Pressure & Charging Water Header Pressure from Value of 955 Psig to 940 Psig ML20094Q6541995-11-21021 November 1995 Application for Amends to Licenses DPR-44 & DPR-56,changing SR for High Pressure Test of the HPCI & RCIC Sys. Administrative Change Proposed to Eliminate Ref to Section Previously Eliminated 1999-09-27
[Table view] |
Text
..
ep+1 *ouq g *, UNITED STATES NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 2006M201 d
3 * * * *
PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY i
4 ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 i
PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 1
- AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 218 i License No. DPR-44 i
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by PECO Energy Company, et al. (the licensee) dated August 27, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (th'. l Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.
4 B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows:
9703030030 970219 PDR ADOCK 05000277 P PDR
1 (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendwnt No. 218, are hereby incorporated in the license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications.
l
- 3. This license amendment is effective es of its date of issuance and is to be implemented within 30 days.
FOR THE N'JCLEAR REGULATORY COMMISSION (L f Johp F.' Stolz, Director /
Pr4 Ject Directorate I-2 Division of Reactor Drojects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 19, 1997 i
l
i s
4 ATTACHMENT TO LICENSE AMENDMENT NO. 218
\
i FACILITY OPERATING LICENSE NO. DPR-44 l l
4 DOCKET NO. 50-277
. l Replace the following page of the Appendix A Technical Specifications with the j enclosed page. The revised areas are indicated by marginal lines. i Remove Insert l 3.10-20 3.10-20 j i ,
i l
l 1
4
_ ... _ _ . _ _ _ _ _ . _ _ . _ . _ _ _ _ _ _ . . _ . . . . ~ . . _ . - . _ . . . _ . . _
'l
- l. .
SON Test-Refueling 3.10.8 :
3.10 SPECIAL OPERATIONS l l
3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling LC0 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/ hot standby position, and operation considered not to be in MODE 2, to allow SOM testing, provided the following requirements are l met: l
- a. LCO 3.3.1.1, " Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a l and 2.e of Table 3.3.1.1-1;
- b. 1. LCO 3.3.2.1, " Control Rod Block Instrumentation," l MODE 2 requirements for Function 2 of '
Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence, DE
- 2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;
- c. Each withdrawn control rod shall be coupled to the associated CRD;
- d. All control rod withdrawals during out of sequence l control rod moves shall be made in notch out mode; !
- e. No other CORE ALTERATIONS are in progress; and l f. CRD charging water header pressure a 940 psig.
4 APPLICABILITY: MODE 5 with the reactor mode switch in startup/ hot standby position.
i f
l l PBAPS UNIT 2 3.10-20 Amendment No, ett( 218 t --. .. . - _ . .
y-,, t p -
UNITED STATES
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
\ . . . . . p/ i PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY i DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 l l' i i
PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 4 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 221 i License No. DPR-56 !
4
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
! A. The application for amendment by PECO Energy Company, et i
al. (the licensee) dated August 27, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the '
Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I.
B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
. Commission;-
C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied..
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. OPR-56 is hereby amended to read as follows:
(2) Technict1 Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.221, are hereby incorporated in the liceriss. PECO shall operate the facility in accordance with the Technical Specifications. '
- 3. This license amendment is effective as of its date of issuance and is to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION L '
40 n F. Stolz, Directo e oject Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 19, 1997 I 1
l i
1 l
l l
4
_ _ . _ _ . . _ _ _ . . . _ _ . _ _ . _ _ . _ _ _ _ _ _ . ~ . _ . _ . . . . ._ _
i i
l ATTACHMENT TO LICENSE AMENDMENT NO. 221 j FACILITY OPERATING LICENSE NO. OPR-56 DOCKET NO. 50-278 i Replace the fnllowing page of the Appendix A Technical Specifications with the j enclosed page. The revised areas are indicated by marginal lines.
8 l
Remove Insert
, 3.10-20 3.10-20 1
SDM Test-Refueling )
3.10.8 '
i 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling l LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/ hot standby
! position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are
- met:
l a. LCO 3.3.1.1, " Reactor Protection System i Instrumentation," MODE 2 requirements for Functions 2.a i
and 2.e of Table 3.3.1.1-1;
- b. 1. LCO 3.3.2.1, " Control Rod Block Instrumentation,"
', MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal 1
i sequence requirements of SR 3.3.2.1.8 changed to
- require the control rod sequence to conform to the SDM test sequence, E i
- 2. Conformance to the approved control rod sequence for l the SDM test is verified by a second licensed :
operator or other qualified member of the technical l i staff; ;
l
- c. Each withdrawn control rod shall be coupled to the associated CRD;
- d. All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode;
- e. No other CORE ALTERATIONS are in progress; and l f. CRD charging water header pressure a 940 psig.
l APPLICABILITY: MODE 5 with the reactor mode switch in startup/ hot standby l position. l l
l PBAPS UNIT 3 3.10-20 Amendment No.X, 221