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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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I I
ATTACHMENT I PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO SURVEILLANCE, AUDIT FREQUENCY AND ADMINISTRATIVE CHANGES l
?
E f
L POWER AUTHORITY OF THE STATE OF NEW YORK
- JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 l
i l
8303020021 830225 -
PDR ADOCK 05000333' PDR;
, _P
~
TABLE 3.6-1b SAFETY RELATED MECHANICAL SNUBBERS g
$ HIGH RADIATION ESPECIALLY O' SNUBBER ACCESSIBLE OR ZONE DIFFICUCT
$ NO. LOCATION ELEVATION INACCESSIBLE DURING SHUTDOWN TO REMOVE e
,$ 10-7B-S3 Crescent Area RilR-45B 239' A NO NO 10-9A-S40 Crescent ?.rea MOV-65B 246' A YES NO l 10- 13A-S112 Reactor Building 315' A NO NO 12"-W20-302-13A .
10-15B-S124A Crescent Area 256' A 'M) NO 10-15B-S124B 16"-W20-302-15B 10-15B-S125A Crescent Area MOV-39B 256' A -
NO NO 10-15B-S125B 10-3B-S153 Crescent Area 232'- A NO NO
" 24"-W20-152-3B 10-35-S221A Reactor Building 336' A NO NO 4"-W20-302-35 ,
10-9A-S254 Crescent Area 262* A NO NO 16"-W20-302-9A 10-9B-S286 Crescent Area 253' A NO NO 16"-W20-302-9B
. 24 "-W20 - 15 2 - 3 B 10-15A-S307 Crescent Area MOV-39A 256' A NO NO 10-15A-S308 -
10-15B-S119A Crescent Area 256' A NO NO 16"-W20-302-15B ,
j 3.11 t at'd) JAFNPP 4.11 (cont'd) 1 B. Crescent Area Ventilation B. Crescent Area Ventilation l'
Crescent area ventilation and cooling Unit coolers serving ECCS
] equipment shall be operable on a components shall be checked .
continuous basis whenever specification for operability once/3 months
. 3.5.A, 3.5.B, and 3.5.C are required
> to be satisfied. 1. When it is determined that two unit coolers serving
- 1. From and after the date that ECCS components in the same more than one unit cooler compartment are made or 1 serving ECCS components in , found inoperable,. reactor the same compartment are made operation may continue for or found to be inoperable, 7 days unless one is made i
all ECCS components in that operable earlier.
compartment shall be considered
}'
Temperature indicator to be inoperable for purposes 2.
! of specification 3.5.A, 3.5.C, controllers shall be
! and 3.5.D. calibrated once/ operating cycle.
C. Battery Room Ventilation I 3. If 3.11.B.1 cannot be met, Battery room ventilation shall be the reactor shall be placed f
operable on a continuous basis in a cold coEidition within whenever specification 3.9.E is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
required to be satisfied.
C. Battery Room Ventilation
- 1. From and after the date that
! one of the battery room ventil- Battery room ventilation equip-ation systems is made or found ment shall be checked for l operability once/ week.
j to be inoperable, its associated l battery shall be considered to j be inoperable for purposes of 1. When it is determined that l specification 3.9.E. one battery room ventilation systesa is inoperable, the l remaining ventialtion system i shall be checked for operability and daily thereafter.
- 2. Temperature transmitters and differential $ressureswitches l sM11 M calhated once/ opera &g cycle.
Amendment No. g 239 f
, _ ._. ~_ _
- c. Th3 r0culto of cctiono teken to correct d3ficisncion occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at
- least once per G months.
- d. The performance of activities required by the Opera-tional Quality Assurance Program to meet the criteria of Appendix "B", 10 CFR 50, at least once per 24 months.
5
- e. The Facility Emergency Plan and implementing procedur?.s at least once per 12 months. l
- f. The Facility Security Plan (including the Safegua'rds Contingency Plan) and implementing procedures at least once per 12 months.
I
- g. Any other area of facility. . operation considered appropriate by the SRC or the Senior Vice President--
Nuclear Generation.
e h.' The Facility Fire Protection Program and implementing procedures at least once per two years.
- i. An independent fire protection and loss of prevention inspection and audit shall be performed annually utilizing either qualified offsite licensee personnel an outside~ fire protection firm. '
- j. An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than
- 3 years.
l 6.5.2.9' AUTHORITY l
The SRC shall report to and advise the Senior Vice President Nuclear Generation on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
6.5.2.10 RECORDS Records will be maintained in accordance with ANSI 18.7-1972. The following whall be prepared, approved and distributed as indicated below:
- a. Minutes of each SRC meeting shall be prepared, approved and forwarded to the Senior Vice President-Nuclear-Generation l within 14 days after the date of the meeting.
- b. Reports of review encompassed by Section 6.5.2.7 above shall be prepared, approved and forwarded to the Senior Vice President-Nuclear-Generation within 14 days following completion of the review.
- c. Audit reports' encompassed by Section 6.5.2.8 above, shall be forwarded to the Senior Vice President-Nuclear-Generation and to the management positions responsible for the areas audited within 30 days after completion of the audit.
Amendment No. 5<f, fdf, g 252 a
. _-..___ _ ,. _ .~ u -.. __ _ _._ . _ _ _ _
N VICE PRESIDENT
$ RESIDENT QUALITY ASSURANCE g MANAGER AND STAFF g J L
" PLANT OPERATING Z REVIEW COMMITTEE ~
]
.O SUPERINTENDENT .
OF POWER
< AND STAFF l
. I I
I I MAIN- I &C OPERATIONS RADIOLOGICAL TECHNICAL SECURITY / SAFETY QA SUPT.
. TENANCE SUPT. SUPT. (SRO) & ENVIRON- SERVICES FIRE PROTECTION & STAFF SUPT. & & AND STAFF MENTAL SERVICES SUPT. &
- SUPT. & STAFF STAFF STAFF SUPT. & STAFF STAFF i
REACTOR 4 w ANALYST SHIFT 1
- TECHNICAL ADVISOR TRAINING SUPERINTENDENT OFFICE .
AND STAFF MANAGER
- s SHIFT SUPERVISOR (SRO)
I SENIOR NUCLEAR FIGURE 6.2-1 OPERATOR (RO)
I POWER AUTHORITY OF THE STATE OF NEW YORK NUCLEAR CONTROL JAMES A. FITZPA't. RICK NUCLEAR POWER PLANT
! OPERATOR (RO) PLANT STAFF ORGANIZATION 1
I !
- Responsibility for performance and
{ AUXILARY NUCLEAR monitoring of the fire protection
! OPERATORS OPERATORS program.
SRO - SENIOR REACTOR OPERATOR I RO - REACTOR OPERATOR i
=- -
t ATTACHMENT II PROPOSED TECHNICAL SPECIFICATION CHANGES RELATED TO .,
SURVEILLANCE, AUDIT FREQUENCY AND ADMINISTRATIVE CHANGES POWER. AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT l
DOCKET NO. 50-333 s
l l
l
S ction I - Deccription of th9 Chenann ,
Table 3.6-lb-(page 156r, " Safety Related Mechanical Snubbers")
has been revised to incorporate a minor renumbering of the snubbers and the addition of a sixteenth snubber.
Figure 6.2-1, " Plant Staff Organization" on page 260 is updated to show that the Security and Safety Superintendent has responsibility for performance and monitoring of the fire protection program, in accordance with our previous commitment.
4 i
Section 4.11.B (page 239, " Crescent Area Ventilation") is revised to require that unit coolers serving ECCS components are checked for operability once per three months, rather.than during
! the surveillance testing of the associated pumps, as currently
! required.
In Section 6.5.2.8(e) on page 252a, the audit frequency for emergency preparedness and safeguards contingency plans is revised to agree with the requirements of parts 73.40(d) and 50.54(t) of Title 10 of the Code of Federal Regulations.
Section II - Purpose of the Changes The changes to Table 3.6-lb will update this list of safety related snubbers to include a new, sixteenth unit. In addition, one of the snubber numbers has been changed for clarity. (Please note that this same page was changed in a previous amendment application dated July 13, 1981. As of this date, this application amendment i
has not been issued by the Commission. The page included in Attachment II of this application supercedes the previously submitted page.)
One of the two changes to Figure 6.2-1 incorpcrates an existing NRC commitment into the FitzPatrick Technical Specifications regarding the Security and Safety Superintendent's job function.
The second changes the " Training Coordinator" block to read
" Training Superintendent and Staff" to agree with current Authority organization and titles.
The current Section 4.11.B (Crescent Area Ventilation) requires excessive testing, is inconsistent with ALARA and does not improve reliability. The proposed test frequency (once every 3 months) corresponds to the frequency stated in the Inservice Inspection Valve Test Program for unit cooler temperature control valves. The present specification results in several tests of unit coolers each month.. This is because current specifications require unit cooler tests with each LPCI, Core Spray and HPCI operability and flow rate test. Personnel performing this testing are therefore required to l
spend additional time in the radiation areas in which these unit I coolers are located. Furthermore, there are heat loads in the i f crescent areas which require that these unit coolers function to l
maintain normal temperatures. These heat loads include ambient
- , . _ , _ _ . , *_ - _ . . _ , . . - . . _ - ..... _ a_ _ L:__.._ _---_,_,,,_.... .
.-. _ _ _ _--. L _._,.._ _ _,_. . ,.,. _,_.m.
1 (wcra woathar) courcso, continuously heated stson supply linsa to HPCI and RCIC,.and non-emergency operation of ECCS components (e.g.
for surveillance testing, shutdown cooling or suppression pool cooling and level maintenance.) Thus, crescent area temperature provides a continuous indication of unit coolers operability. A
- quarterly surveillance test adequately ensures reliability.
i In Section 6.5.2.8(e) (page 252a), the audit frequencies for emergency preparedness and safeguards contingency plans 1 (References f and g) are revised to agree with Title 10 of the Code of Federal Regulations, parts 50.54(t) 73.40(d), respectively. We were notified of the need for this change via Reference f and g.
l This is clarifying, and made at the request of the Commission.
! Section III - Impact of the Changes Figure 6.2-1 and Table 3.6-lb will be updated to reflect changes already in effect at FitzPatrick and therefore will not impact plant operation.
The reduced surveillance testing required by Section 4.11.B will reduce personnel radiation exposure while maintaining a high level of reliability and operability for these unit coolers.
These changes will not have any impact on the environment. The changes as proposed will not impact the Fira Protection Program at the James A. FitzPatrick Nuclear-Power Plant.
Section IV - Implementation of the Change I
Reduced personnel radiation exposure will result from reduced surveillance test requirements.
Section V - Conclusion The incorporation of these changes: a) will not change the
, probability nor the consequences of an accident or malfunction of equipment important to safety as previously evaluated in the Safety Analysis Report; b) will not increase the possibility of an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical Specification; and d) does not constitute an unreviewed safety question.
i
'Section VI - R7fercncon (a) Jcoto A. FitzPatrick Nuclear Pow 3r Plant Final Shfoty Analycio Report (FSAR).
(b) James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER).
(c) J.P. Bayne (PASNY) to T.A. Ippolito (USNRC) dated July 13, 1981 regarding Proposed Technical Specification Changes Related to Snubber Surveillene (JPN-81-51).
(d) C.A. McNeill, Jr. (PASNY) to R.C. Haynes (USNRC) dated May 28, 1982 regarding I.E. Bulletin No. 81-01, (JAFP-82-0577).
(e) I.E. Bulletin No. 81-01, Surveillance of Mechanical Snubbers" dated January 27, 1981.
(f) Generic Letter No. 82-17, D.G. Eisenhut (NRC) to all Licensees dated October 1, 1982. . j (g) Generic Letter No. 82-23, D.G. Eisenhut (NRC) to all Licensees dated October 30, 1982.
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