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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day ML20107M4511996-04-24024 April 1996 Proposed Tech Specs 3.11.B/4.11.B Re Crescent Area Ventilation ML20101H6741996-03-27027 March 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J at Plant & Clarifies Numerical Value of Allowable Containment Lrt as 1.5% Per Day ML20101H3821996-03-22022 March 1996 Proposed TS Table 3.2-2 Re Core & Containment Cooling Sys Initiation & Control Instrumentation Operability Requirements ML20101F8411996-03-22022 March 1996 Proposed Tech Specs,Implementing BWROG Option I-D long-term Solution for Thermal Hydraulic Stability ML20097A2271996-02-0101 February 1996 Proposed Tech Specs,Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20100C2991996-01-25025 January 1996 Proposed Tech Specs Re EDGs Surveillance Testing ML20097J6691996-01-25025 January 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellaneous Surveillance Test Intervals to Accommodate 24- Month Operating Cycles ML20095F7091995-12-14014 December 1995 Proposed Tech Specs,Incorporating IST Requirements of Section XI of ASME Boiler & Pressure Vessel Code ML20094R6981995-11-30030 November 1995 Proposed Tech Specs,Extending Surveillance Test Intervals for SLC Sys to Support 24 Month Operating Cycles ML20094B6641995-10-25025 October 1995 Proposed Tech Specs Extending Containment Sys Surveillance Test Intervals to Accommodate 24 Month Operating Cycles ML20092H5401995-09-15015 September 1995 Proposed Tech Specs Extending Surveillance Test Intervals for Auxiliary Electrical Sys to Support 24 Month Operating Cycles ML20086P6561995-07-21021 July 1995 Proposed Tech Specs Re Replacement of title-specific List of PORC Members W/More General Statement of Membership Requirements 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] |
Text
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CORRECTED TECHNICAL SPECIFICATION PAGES New York Power Authority JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR 59 ggg50ggobOb [3 P
ar JAFNPP TABLE 3.7 (Sh.6 of 15) _
PRIMARY CONTAINMENT ISOLATION VALVES -
' CONTAINMENT PENETRATION VALVE ISOLATION CLOSE TIME NORRhAL -REMARKS PENETRATION FUNCTION NUMBER- S!GNAL (SEC) (5) - STATUS (7) 31Bd Drywell 27SOV-135D .A,F,R,Z N/A Open From elev. 293' to atmospiere Radiation Monitors '
sample 27SOV-135B . A.F,R,Z N/A Open Note 12.
(Suction) 35B Traversing 07SOV-104A. A.F.R N/A Open Notes 8,14, in e Probe "A* 07EV-104A R N/A Open Notes 14,15.
35C Traversmg 07SOV-104C A.F.R N/A Open Notes 8,14 In-core Probe "C* 07EV-104C R N/A Open Notes 14,15.
35D Traversing 07SOV-1048 A.F.R N/A Open Notes 8,14.
In-core -
Probe *B" 07EV-104B R N/A Open ' Notes 14,15.
Amendment No. [, f.1[,1[
203
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JAFNPP
,-. Notes For 'lable 3.71
.
.d
- 11. Valve 20AOV.95 opens during pump out of the drywell equipment sump. Automatic 'f Isolation signals A and F override an open signal that might be present for sump pump out. .
- 12. Radiation monitors used for sampling lodine, particulate, and gaseous are as follows:
Radiation .
Monitors Sample i
17 RM 101 A lodine
.17.RM-1018 17.RM 102A Particulate 17.RM.102B 17 RM.103A Gaseous 17 RM.103B
- 13. Isolation signais A, F, and Z may be manually overridden by keylock switch on the i Monitoring and Analysis Panel (MAP) located in the relay room.
- 14. Traversing in-core Probe (TIP) penetrations are isolated by a guide tube and valve assembly which includes a solenoid operated ball valve and an explosive shear valve <
designed to sever and seal the TIP tubing and TIP detector helix.
- 15. The explosive shear valves are not normally actuated and require replacement parts and maintenance activity in order to open the valves following actuation.
Amendment No. 46, p, ipd 209
JAFNPP' s TABLE 4.7-2 EXCEPTION TO TYPE C TESTS -
The following penetrations are excepted from Type C testing regthvir.wiE VALVE LOCAL LEAK RATE TEST PERFORMED CONTAINMENT - PENETRATION FUNCTION NUMBER-PENETRATION Main Steam - . 29AOV-80A The inboard valves wil be tested in the reverse direction. Pressure wEl be 7A apphed between the isolation valves and leakage enessured. A water seal 78 - 29AOV-808 ~
29AOV-80C of 25 psig wil be used on the inboard valve to determine the outboard 7C valve's leak rate. (limit 11.5 SCFH st 25 psig.) ~
7D ' 29AOV-80D
' 29AOV-86A 29AOV-86B 29AOV-86C 29AOV-860 27AOV-112 These valves wil be tested in tise reverse a;.Mi.s 25 Drywell Purge Inlet (Airand/or 27AOV-131A Nitrogen) 27AOV.131B
- 27AOV-113 These valves wil be tested in the reverse direction.
26A'& 26B Drywell Purge Inlet (Air and/or 27MOV-122 Nitrogen)
Various Wil not be tested as lines are sealed by process fluid.
30A lostrumentation 07EV-104A This valve is an explosive shear valve vnkh cannct be Type C tested.
35B Traversing Incro Probe "A*
Amendment No.f f. ty6,1[.1/5 211
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i REVISION 1 TO SAFETY EVALUATION 6
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1 New York Power Authority .
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No 50333 ,
DPR 59 .
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i Attachment 11
- SAFETYEVALUATION REVISION 1 Page 1 of 3 1, DESCRIPTION OF THE PROPOSED CHANGES f The proposed changes to the James A. RtzPatrick Technical Specifications revise Table 3.7-1,
" Primary Containment Isolation Valves,' and Table 4.7 2,
- Exception to Type C Testc." The l ,
changes are as follows:
Table 3.71, paDe 203 ,
t
- 1. Delete penetrations X 35A and X 35E. i
- 2. Revise valve numbers as follows:
Penetration From valve number To valve number t 358 07NM 104B 07SOV 104A 07NM-104B 07EV 104A :
35C 07NM 1040 07SOV 1040 07NM 1040 07EV 104C
{
35D 07NM 104D 07SOV 104B l 07NM-104D 07EV 104B .
Table 3.71, page 209 :
Delete the last sentence in Note 14. The sentence to be deleted reads as follows:
"The guide tube and valve assemblies are designated 07NM 104 A, B, C, and D for [
penetrations 35A, B, C, and D, respectively." {
Table 4.7 2, page 211 f
- 1. Delete penetration 35A. .
L 2. Penetration 35B Revise the valve number from *07NM-104B* to *07EV 104A."
Table 4.7 2, page 212
- 1. Penetration 350 Revise the valve number from *07NM 104C" to *07EV 104C."
- 2. Penetration 35D Revise the valve number from *07NM-104D* to *07EV 104B.*
II. PURPOSE OF THE PROPOSED CHANGES The Traversing incore Probe (TIP) system is used to calibrate the Local Power Range Monitors +
g (LPRMs). Durin0 the 1990 refueling outage the existing system will be replaced with a new state-of iho-art system. The new system will improve overall TIP system reliability, availability, and L accuracy.
L I
l Attachment 11 ,
. SAFETY EVALUATION REVISION 1 l Page 2 of 3 The modification replaces the four existing TIP drive units with three drive units. The helical shield cabling will be replaced with a titanium shield cable. Changing from a four channel system to a three channel system requires the use of one less contalnrnent penetration. As a result, i penetration X 35A will be capped. The titanium shielding, which does not require a nitrogen l i b'anket, permits the removal of the TIP system's nitrogen purge equipment. Penetration X 35E, which accommodated the TIP nitrogen purge line, will also be capped. 6 In addition, editorial changes were also made to correctly identify the containment isolation valve associated with Penetrations 358, C, and D.
1 111. IMPACT OF THE PROPOSED CHANGES The proposed changes revise Tables 3.71 and 4.7 2 to delete two penetrations, X 35A and X 35E, which will be capped as a result of the TIP system modification. The capping of these penetrations is not a safety concern because the replacement of an active isolation valve with a j passive barrier is a more reliab!e containment isolation method. The capped TIP penetrations will l be subjected to a Type A integrated leak rate test with visual inspection prior to plant restart and ;
periodic testing in accordance with the requirements of 10 CFR 50, Appendix J. I
)
The changes do not alter the conclusions of the plant's accident analysos as documented in the FSAR or the NRC staff's SER nor are they considered a significant hazard consideration.
1 IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the James A. FitzPatrick Nuclear Power Plant in accordance with this proposed amendment would not involve a significant hazards consideration, as defined in 10 CFR 50.92, '
sinco the proposed changes would not:
1
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated. The changes update Tables 3.71 and 4.7 2 in support of a plant modification which caps ponetrations X 35A and X 35E. These penetrations will be leak tcsted during the l integrated leak rate test of the containment in accordance with the requirements of 10 CFR 50, Appendix J. The capping of these penetrations do not impact the plant's accident analyses as documented in the FSAR or the NRC staff's SER.
i
! 2. create the possibility of a new or different kind of accident from those previously evaluated. j l The capping of these two containment penetrations improves containment isolation i l because a passive barrier is less likely to fall than an active Isolation valve. These changes l l do not introduce any new active failure modes and can not create a new or different kind of accident, i
- 3. Involve a significant reduction in the margin of safety. The propcsed changes cap two penetrations which are no longer required by the TIP system. Thece changes do not reduce the margin of safoty, since a passive barrier is a more reliablo method of containment ;
isolation ther an active isolation valve.
l
Attachment 11
~
r SAFETY EVALUATION REVISION 1 :
Page 3 of 3 V. IMPLEMENTATION OF THE PROPOSED CHANGES
(
Implementation of the proposed changes will not impact the Al. ARA Program at FitzPatrick, nor will the changes impact the environment.
VI. CONCLUSION :
These changes, as proposed, do not constitute an unreviewed safety question as defined in 10 CFR 50.59. That is, they:
- a. will not increase the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report;
- b. will not increase the possibility for an accident or malfunction of a different type from any evaluated previously in the safety analysis report;
- c. Will not reduce the margin of safety as defined in the basis for any technical specification; and l_ d. Involves no significant hazards consideration, as delined in 10 CFR 50.92.
I Vll. REFERENCES i 1. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report, Sections
! 5.2A.6 and 7.5.9.
l
- 2. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20,1972 and Supplements.
( 3. James A. FitzPatrick Nuclear Power Plant Traversing Incore Probe (TIP) System Upgrade Conceptual Design Package Modification Number F189 253, December 1989.
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