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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20205Q8801999-04-13013 April 1999 Proposed Tech Specs Page 5-9,replacing Operational TSs with Permanently Defueled TSs ML20154E3441998-10-0202 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-39 & DPR-48,eliminating License Conditions No Longer Applicable & Replacing Existing Operational Custom TS with Permanently Defueled TS ML20217H9451998-03-30030 March 1998 Proposed Tech Specs Restoring Plant Custom TS Replaced W/ Improved TS by Previous Amend & Reinstating License Condition Deleted by That Previous Amend ML20202H3641997-11-28028 November 1997 Proposed Improved TSs Using Guidance Provided in NUREG-1431 ML20199D6251997-11-10010 November 1997 Proposed Improved TS Bases Changes & Supporting Info & Final Proposed TS Bases for Section 3.3,including Revised Table of Contents & List of Effective Pages ML20211B9941997-08-0606 August 1997 Proposed Improved Tech Specs Re Draft SER for Zion Station Conversion,Per NUREG-1431 ML20196G8781997-07-18018 July 1997 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Using Guidance Provided in NUREG-1431, Std Ts,Westinghouse Plants ML20134J3641996-11-0808 November 1996 Proposed Tech Specs Re Rquirements Governing RCS Pressure & Temp Limits ML20134G5921996-11-0707 November 1996 Proposed Tech Specs 3.13.1.A Re Limiting Operation for Operation ML20134G4141996-11-0707 November 1996 Proposed Tech Specs Table 3.7-1 Re Reduced Power Range Neutron Flux High Setpoint Trip ML20134G3401996-11-0707 November 1996 Proposed Tech Specs 4.3.1.A.4.b Re Surveillance Requirement ML20129J7731996-11-0101 November 1996 Proposed Tech Specs Modifying Section 3.15.2.A & Section 4.15.2.A of TS ML20128Q8891996-10-14014 October 1996 Proposed Tech Specs 3.3.2.G Re Limiting Condition for Operation & 4.3.2.G Re Surveillance Requirements ML20128L8371996-10-0404 October 1996 Proposed Tech Specs Re Implementation of Option B to 10CFR50,App J ML20128L7831996-10-0404 October 1996 Proposed Tech Specs Modifying F* Distance Definition ML20128H3011996-10-0404 October 1996 Proposed Tech Specs,Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels to TS ML20059H5811994-01-19019 January 1994 Proposed Tech Specs Revising RCS Temperature Required for Reactor Criticality,In Addition to Editorial Changes in Affected Specifications ML20058C3031993-11-19019 November 1993 Proposed Tech Specs Changing LTOP of Reactor Vessel ML20058A2651993-11-10010 November 1993 Proposed Tech Specs Re Limitations on Radioactive Matl Released in Liquid & Gaseous Effluents & New 10CFR21 ML20059H9541993-11-0404 November 1993 Proposed Tech Specs Revising Surveillance Frequency & Acceptance Criteria ML20056F7291993-08-23023 August 1993 Proposed Tech Specs for Implementation of Latest Rev to 10CFR20, Stds for Protection Against Radiation ML20127N0531992-12-22022 December 1992 Proposed Tech Specs to Relocate Fire Protection TSs to an owner-controlled Document Consistent W/Guidance Provided in Generic Ltrs 86-10 & 88-12 ML20127C6521992-09-0101 September 1992 Proposed TS for License Amend Request 92-03 Re Reactor Vessel Integrity & RCS Heatup & Cooldown Limitation Curves ML20248G1221989-09-29029 September 1989 Proposed Tech Spec Page 210 Re Containment Isolation ML20248B3991989-09-25025 September 1989 Proposed Tech Specs to App a Re Section 3.9 Containment Isolation ML20247D0841989-07-18018 July 1989 Proposed Tech Specs,Removing Section 3/4.17.2, Aircraft Fire Detection Sys ML20246D4131989-07-0606 July 1989 Proposed Tech Spec Section 3.15, Auxiliary Electric Power Supply ML20245C6151989-06-13013 June 1989 Proposed Tech Specs Revising Sections 4.0.3 & 4.0.4 Re Applicability of Limiting Conditions for Operations & Surveillance Requirements ML20247M9681989-06-0202 June 1989 Proposed Tech Specs,Revising Tech Spec Section 4.3 to Allow Plant Steam Generator Tubes to Be Repaired Through Installation of Welded Sleeve ML20246N3071989-05-11011 May 1989 Proposed Tech Specs Modifying Section 3.15.2.C to Extend one-time Maint Overhaul to 45 Days to Perform Extensive 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[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20216G1351999-09-23023 September 1999 Rev 5 to Chapter 12 of Zion Annex Odcm ML20209F8321999-06-30030 June 1999 Rev 4,Chapter 12 of ODCM for Zion Annex ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20205Q8801999-04-13013 April 1999 Proposed Tech Specs Page 5-9,replacing Operational TSs with Permanently Defueled TSs ML20154E3441998-10-0202 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-39 & DPR-48,eliminating License Conditions No Longer Applicable & Replacing Existing Operational Custom TS with Permanently Defueled TS ML18068A7121998-07-31031 July 1998 Rev 3 to Chapter 12 of Zion Station Odcm. ML20217N9661998-03-31031 March 1998 Revs to ODCM for Zion Station,Including Rev 2 to Chapters 10 & 12 ML20217H9451998-03-30030 March 1998 Proposed Tech Specs Restoring Plant Custom TS Replaced W/ Improved TS by Previous Amend & Reinstating License Condition Deleted by That Previous Amend ML20216G8981998-03-16016 March 1998 Certified Fuel Handler Training & Retraining Program ML20202H3641997-11-28028 November 1997 Proposed Improved TSs Using Guidance Provided in NUREG-1431 ML20199D6251997-11-10010 November 1997 Proposed Improved TS Bases Changes & Supporting Info & Final Proposed TS Bases for Section 3.3,including Revised Table of Contents & List of Effective Pages ML20216H9041997-10-31031 October 1997 Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F ML20212B4761997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Dept Start- Up Readiness Assessment Guideline ML20212B4421997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Plan ML20212B4471997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Scope Mgt Guideline ML20212B4601997-10-22022 October 1997 Rev 3 to Zion Nuclear Station Recovery Program,Sys Readiness Review ML20211B4831997-09-0505 September 1997 Restart Action Plan ML20211B9941997-08-0606 August 1997 Proposed Improved Tech Specs Re Draft SER for Zion Station Conversion,Per NUREG-1431 ML20196G8781997-07-18018 July 1997 Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program ML20140D8071997-06-0606 June 1997 Proposed Tech Specs Using Guidance Provided in NUREG-1431,to Produce Set of Improved TS for Plant ML20140C4151997-06-0505 June 1997 Rev 1 to Zion Nuclear Station Recovery Plan ML20148B7371997-05-0808 May 1997 Proposed Tech Specs Re Addition of Discussion of Position & Duties of Licensed Operators & Senior Licensed Operators to Section 5.3, Qualification ML20134J2971997-02-0303 February 1997 Proposed Tech Specs Suppl to 960920 Application for Amend to Licenses DPR-39 & DPR-48,providing Annotated & Clean Copies of ITS Pp Affected by Proposed Amend ML20216E6041997-01-31031 January 1997 Amend 4 to Zion Station Fire Protection Rept ML20137B4691997-01-31031 January 1997 Rev 1.9 to Chapter 10, Zion Annex Index & Rev 1.8 to Chapter 12, Radioactive Effluent Technical Stds ML20134G0991997-01-27027 January 1997 Proposed Tech Specs Re Revising TS Such That Use of Entire Abb/Ce TR,CEN-629-P,would Be Authorized as Governing Document for Installing CE Sleeves in SG Tubes ML20133D0901997-01-0202 January 1997 Proposed Tech Specs Using Guidance in NUREG-1431 to Produce Improved TSs ML20132B8331996-12-11011 December 1996 Proposed Tech Specs Completely Revising TS Using Guidance Provided in NUREG-1431, Std Ts,Westinghouse Plants ML20134J3641996-11-0808 November 1996 Proposed Tech Specs Re Rquirements Governing RCS Pressure & Temp Limits ML20134G5921996-11-0707 November 1996 Proposed Tech Specs 3.13.1.A Re Limiting Operation for Operation ML20134G4141996-11-0707 November 1996 Proposed Tech Specs Table 3.7-1 Re Reduced Power Range Neutron Flux High Setpoint Trip ML20134G3401996-11-0707 November 1996 Proposed Tech Specs 4.3.1.A.4.b Re Surveillance Requirement ML20129J7731996-11-0101 November 1996 Proposed Tech Specs Modifying Section 3.15.2.A & Section 4.15.2.A of TS ML20134H4591996-10-31031 October 1996 Rev 1.8 to Chapter 10 Odcm,Zion Annex Index ML20128Q8891996-10-14014 October 1996 Proposed Tech Specs 3.3.2.G Re Limiting Condition for Operation & 4.3.2.G Re Surveillance Requirements ML20128L8371996-10-0404 October 1996 Proposed Tech Specs Re Implementation of Option B to 10CFR50,App J ML20128H3011996-10-0404 October 1996 Proposed Tech Specs,Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels to TS ML20128L7831996-10-0404 October 1996 Proposed Tech Specs Modifying F* Distance Definition ML20129E5621996-09-30030 September 1996 Rev 1.1 to Chapter 11 to Odcm,Zion Annex Index ML20129J4891995-10-0404 October 1995 On-Site Review for ODCM Revision ML20059H5811994-01-19019 January 1994 Proposed Tech Specs Revising RCS Temperature Required for Reactor Criticality,In Addition to Editorial Changes in Affected Specifications ML20058C3031993-11-19019 November 1993 Proposed Tech Specs Changing LTOP of Reactor Vessel ML20058A2651993-11-10010 November 1993 Proposed Tech Specs Re Limitations on Radioactive Matl Released in Liquid & Gaseous Effluents & New 10CFR21 ML20059H9541993-11-0404 November 1993 Proposed Tech Specs Revising Surveillance Frequency & Acceptance Criteria ML20058E8751993-09-0303 September 1993 Revised AOP-6.3, Loss of RHR Shutdown Cooling ML20056F7291993-08-23023 August 1993 Proposed Tech Specs for Implementation of Latest Rev to 10CFR20, Stds for Protection Against Radiation ML20056H0281993-08-20020 August 1993 Errata to Chapter 12 to ODCM, Including Revised Table 12.2-1,12.2-3 & 12.5-1 ML20056G8131993-06-30030 June 1993 Pump & Valve Inservice Testing Plan for Zion Nuclear Generating Station Units 1 & 2 ML20058E8351993-06-10010 June 1993 Revised AOP-7.4, Control Room Inaccessibility ML20127D0691992-12-30030 December 1992 Corporate Emergency Response Organization Required Reading Package 92-11 1999-09-23
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. . i ATTACIMDCL1 EROFDSID_IRAliGES To APERfDIX_A IICDIICAL_SPICIIICAIIDti SECT 10tL4,.2xL L1 HORLC_ ACID _EYSIDI EagnisLMo.d111ed 43 44 East (ALAdded 11one EngelsLDeleted lione 5162K OG10110100 SG092G pg AtiOCK0*300,{U
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I LIMITING CONDITION FOR OPERATION - SURVEILLANCE REQUIREMENT i t
l 3.2.1.F.1. (Continued) 4.2.1.F.1. (Continued)
I l b. One boric acid pig shall be OPERATING b. Each boric acid pump shall be .l l and the standby pump shall be OPERABLE. functionally tested weekly. 6
}
. I i c. One channel of heat tracing shall be c. Heat trace for the Boric Acid Tank to l OPERATING and the remaining channel Charging Pump suction flow path shall be !
l shall be OPERABLE on at least one flow demonstrated OPERABLE:
i pathdrors the OPERABLE Boric Acid Tank 8
to the Charging Pump suction. 1) At least once per day by:
- *) ' Verifying that one channel is energized, and
, b) Verifying the redundant channel
$e as available.
i I
- 2) At least once per week by:
i a) Checking the associated local
! alarms, and b) Energizing each heat tracing I
channel.
- 2. During reactor operation, including recovery 2. Not Applicable:
l from an inadvertant trip, the requirements i of 3.2.1.F.1 may be modified as follows:
I j a. One boric acid pump may be inoperable a. When it is detenr.ined that one of the
! g for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided that the standby two boric acid pumps is inoperable, the
} l pu=p is OPERABLE. standby pump shall be placed in operation immediately.
- b. One channel of heat tracing may be b. When it is determined that one of the 1 inoperable for 7 dr.ys provided that the two channels of heat tracing is j remaining channel of heat tracing is inoperable, the remaining channel shall
- l OPERABLE. be placed in operation immediately. The
'I operation of the remaining channel of I heat tracing shall~ be verified once a 1 shift.
I 13090 43 TSC 88-03 e 0921A
. . . . - - - - . - - - - .. Y,
k * -
t j i . I LIMITING CONDITION FOR OPERATION c
' SURVEILLANCE REQUIREMENT h 3.2.1.F. (Continued) 4.2.1.F. (Continued)
! 3. If these conditions cannot be met the 3. Not Applicable j reactor shall be borated to the COLD '
SHUT 00WN boron concentration within four -
hours.
-f.
l G. Primary System Boron Concentration Changes G. Primary System Boron Concentration Changes j during COLD SHUTDOWN. during COLD SHUTDOWN. .!
l I When a boration or dilution operation *s in The operation of at least one reactor coolant i progress, at least one reactor coolant pump or pump or one residual heat removal loop shall be s ; one residual heat removal loop shall be verified before the start of a boration or
- ; OPERATING. dilution operation.
l s
' H. Reactivity Anomalies H. Reactivity Anomalies -
A normalization of the computed boron Reactivity anomaly evaluation! shall be 1 concentration ~as a function of burnup shall be performed following startups after shutdowr.s of compared with the actual boron concentration of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or longer duration but shall not be l
the coolant. If the difference between the required more than once if more than one such I observed and predicted steady-state shutdown occurs in a two month period.
} concentrations reaches the equivalent of one l percent in reactivity, the NRC shall be notified .
3 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and an evaluation as to the -
cause of the discrepancy shall be made and reported to the NRC within 30 days.
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! 13090 44 TSC 88-03
{ 0921A
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ATIACB m T 2 j i
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] KYMUATION of SIGNIFICANT HAZARDS cot [SIDERAIlgli ERQPDSID_CliAttGIS TO ZIotLIECHti1 CAL {
SPICIE1CAIlotLAPPEND1X A - SECTION. 4.it4L1 l
- BORIC ACIILSYST111
t l I i i DES.CRIEIlm_Of_ AMENDMENT REGIEST !
d i ;
An amendment to the Zion racility Operating License is proposed to l clarify and upgrade the surveillance requirement 1 for the heat trace system associated with Boric Acid Tank (BAT) and Charging Pump suction lines.
1 t
BACEGEQ11HD [
10 CTR 50.92 states that a proposed amendment will involve a no l i significant hasards consideration if the proposed amendment does nots f*
f i
(1) Involve a significant increase in the probability or consequences [
of an accident previously evaluated; or i
(2) Czente the possibility of a new or different kind of accideat from !
(
any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
- The following discussion address these three criteria and demonstrates that the proposed amendment involves a no significant hasards consideration.
I i DA SI S_ EOR _R0_S I G'LI EICNIT_B AZ ARD.S_CQttSIDEEAIlotLDEIERMINATILtl j DISCUSSION ITEM _1 This change adds the surveillance requirement of verifying daily at ,
q 1 east one channel is energised and the redundant channel available. This is a !
- significant increase over the current surveillance requirements of functionally i testing 1. eat tracing operation weekly. In addition, a requirement to ENERGIZE !
j each heat trace channel weekly provides a more specific requirement rather than .
to functionally test the operation of the heat trace system and a.larm circuits !
i weekly. The control room annunciator has been deleted from the surveillance requirements since it is not required by Standard Technical Specification and ,
is not considered necessary to ensure operability of the heat trace system.
The annunciator is neither safety-related nor reliability related. l iI
Because this proposed change involvi, the expansion and clarification of the affected section, the example (11) of 48 FR 14869 is , applicable in this instance. Example (11) reads as follows: "A change that constitutes an additional limitation, restriction, or control not presently in Technical Specifications for example a more stringent surveillance requirement."
DISGSSI.Gi - IIDLZ This propos. A change does not involve a significant increase in the probability or consequences of an accident previously evaluated, since it increases the reliability of heat trace operations by requiring more frequent surveillance of system operations and removes ambiguous testing requirements.
Also, since the change does not create a change in system operation, a new or different kind of accident from those previously evaluated in the FSAR la not created.
DISGSSIQi - ITDL1 The proposed change will increase the margin of safety since the change is more conservative than is currently than is currently required by Technical Specification. Specifically, the heat trace for the Boric Acid Tanks to the Charging Pumps suction lines are verified operable daily versus weekly. Thus, this change does not involve a reduction in the margin of safety.
5162K