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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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Attachment I to JPN-93-083 PROPOSED TECHNICAL SPECIFICATION CHANGES DIESEL FUEL OlL SAMPLING CLARIFICATION ,
(JPTS-93-001) 1 J
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New York Power Authority J l
JAMES A. FITZPATRICK NUCLEAR POWER PLANT Docket No. 50-333 DPR-59 9401100105 931222 I
' l PDR ADOCK 05000333 P PDR d 'I a
JAFNPP A. Hioh Pressure Water Fire Protection System (Cont'd) A. Hiah Pressure Water Fire Protection System (Cont'd)
- 3. If 1. above cannot be fulfilled, place the reactor in Hot item Freauency Standby within six (6) hours and in Cold Shutdown within the following thirty (30) hours. h. Fire pump diesel engine Once/ Month by verifying the fuel storage tank contains at least 172 gallons of fuel.
- i. Diesel fuel from each tank is Once/ Quarter l within the acceptable limits for quality as per the following:
Flash Point 'F 125'F min.
Pour Point 'F 10*F max.
Water & Sediment 0.05% max.
Ash 0.01 % max.
Distillation 90% Point 540 min.
Viscosity (SSU) @ 100*F 40 max.
Sulfur 1 % max.
Copper Strip Corrosion No. 3 max.
Cetane # 35 min.
- j. Fire pump diesel engine by Once/18 months inspection during shut down in accordance with procedures prepared in conjunction with manufacturers recommendations and verifying the diesel, starts from ambient conditions on the auto start signal and operates for A20 minutes while loaded with the fire pump.
Amendment No. 3474f',1907 244c
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Attachm:nt 11 to JPN-93-083 SAFETY EVALUATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGES DIESEL FUEL OIL SAMPLING CLARIFICATION UPTS-93-001)
- 1. DESCRIPTION OF THE PROPOSED CHANGE The proposed change to the James A. FitzPatrick Technical Specifications is addressed below.
Minor changes in format, such as type font, margins or hyphenation, are not described in this submittal. These changes are typographicalin nature and do not affect the content of the Technical Specifications.
Paae 244c. Soecification 4.12.A.1.i Delete the words "obtained in accordance with ASTM-D270-65."
II. PURPOSE OF THE PROPOSED CHANGE The proposed change to the Technical Specifications removes the reference to American Society for Testing and Materials (ASTM) Standard D 270-65 (Reference 1) from Surveillance Requirement 4.12.A.1.i. ASTM D 270-65, which specifies procedures to draw a representative fuel oil sample, has been superseded and is no I longer in effect. Surveillance Procedure PSP-7 (Reference 2) currently requires sampling in accordance with ASTM D 270-65 but notes that it has been superseded by ASTM D 4057-88 (Reference 3). The proposed change makes Surveillance Requirement 4.12.A.1.i consistent with fuel oil Surveillance Requirement 4.9.C.1, for the emergency diesel generators, by adopting the current industry fuel oil sampling standard (Reference 3). There are no changes to the acceptance criteria for fuel oil quality which are based on ASTM D 975-81 (Reference 4).
Ill. SAFETY IMPLICATIONS OF THE PROPOSED CHANGE Removal of ASTM D 270-65 as the method to sample diesel fuel oil has no adverse affects on plant safety. The proposed change will remove an unnecessary restriction on diesel fuel oil sampling by removing ASTM D 270-65 frorn Surveillance Requirement 4.12.A.1.i. The change is consistent with Surveillance Requirement 4.9.C.1 for the Emergency Diesel Generators (EDG) and the Standard Technical Specifications (STS) (Reference 5).
Improved Fuel Oil Sampling Flexibility Removing reference to ASTM D 270-65 from Surveillance Requirement 4.12.A.1.i will allow ASTM D 4057-88 to be used as the sampling method for the diesel fire pump fuel oil. ASTM D 4057-88, " covers procedures for obtaining representative samples of stocks or shipments of uniform petroleum products ..." The proposed !
change provides a positive safety benefit by allowing the current industry '
standard for fuel oil sampling to be adopted. The proposed change deletes the referei ..e to an industry standard so that adoption of subsequent industry standards will not require a license amendment.
4 I
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Attachm:nt ll to JPN-93-083 SAFETY EVALUATION ,
Page 2 of 4 )
Improved Consistency with the EDG Surveillance Requirement and the STS i
Surveillance Requirement 4.9.C.1 establishes quality requirements for EDG fuel oil that are identical to Surveillance Requirement 4.12.A.1.i. However, Surveillance i Requirement 4.9.C.1 does not require a specific standard for diesel fuel oil sampling. The removal of ASTM D 270-65 makes Surveiliance Requireinent 4.12.A.1.i consistent with Surveillance Requirement 4.9.C.1.
STS Surveillance Requirement 3.8.3.3 specifies fuel oil sampling in accordance with the Diesel Fuel Oil Testing Program. The description of this program in the STS Bases identifies several standards but no specific standard for sampling fuel oil. The STS Bases does reference ASTM D 975-(undated) for fuel oil properties. '
The current standard, ASTM D 975-92 (Reference 6), references ASTM D 4057-(undated) for the sampling method. The proposed change is consistent since it removes ASTM D 270-65 provio.og the flexibility to adopt the applicable industry standard, ASTM D 4057-88. Providing consistency within the Technical Specifications and using the STS to evaluate Technical Specification changes will not decrease plant safety. ,
The changes will not require modification of any plant structures, systems or components and will not alter the conclusions of the plant's accident analyses as ;
documented in the FSAR or the NRC staff SER.
IV. EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATION Operation of the FitzPatrick plant in accordance with the proposed Amendment would not involve a significant hazards consideration as defined in 10 CFR 50.92, since it would not:
- 1. involve a significant increase in the probability or consequences of an accident previously evaluated.
Plant accident analyses are not affected by the Technical Specification change.
The change removes reference to ASTM D 270-65 as the method for obtaining ;
samples of diesel fuel oil from Surveillance Requirement 4.12.A.1.i. The '
American Society for Testing and Materials has superseded ASTM D 270-65 with ASTM D 4057. The proposed change provides improved flexibility to adopt standards as they are issued without requiring a license amendment and makes Surveillance Requirement 4.12.A.1.i consistent with both Surveillance Requirement 4.9.C.1 for the EDG and the STS. The nature of this change will not cause any increase in the probability or consequences of previously evaluated ,
accidents.
- 2. create the possibility of a new or different kind of accident from those previously evaluated.
The proposed change involves no hardware modifications to any plant structures, systems or components. The change removes reference to ASTM D 270-65 as
, ,, . , , - -. . . . .. _. . - _ . , _,.s. _
5 14- c Attachmsnt 11 to JPN-93-083. .!
V SAFETY EVALUATION I Page 3 of 4 a .
' the method for obtaining samples of diesel fuel oil from Surveillance Requirement .
4.12.A.1.i. ' The American Society for Testing and Materials has superseded j ASTM D 270-65 with ASTM D 4057. The nature of this change is such that no? ~i new or different kind of accident can be created. ",
I
- 3. involve's significant reduction in the margin of safety.
The proposed change will not cause a reduction in the margin of safety. The - .l results of the plant accident analyses continue to bound operation under the- l proposed changes so there is no reduction in the margin of safety. The change ;
removes reference to ASTM D 270-65 to allow the use of ASTM D 4057-88 as - i the method for obtaining samples of diesel fire pump fuel oil. The change will :
make Survei_Ilance Requirement 4,12.A.1.i consistent with existing Surveillance )
Requirement 4.9.C.1 for the EDG and allow current standards to be used for fuel- .
oil sampling. Revisions of this nature will not cause a reduction in the margin of. j safety. !
V. IMPLEMENTATION OF THE PROPOSED CHANGES 'i Implementation of the proposed changes removes reference to ASTM D 270-65 a's i the method for obtaining samples of diesel fuel oil from Surveillance Requirement 'l 4.12.A.1.i. This change will not affect the ALARA or Fire Protection Programs at the . 'l FitzPatrick plant, nor will the changes affect the environment. 1 VI. CONCLUSION The changes, as proposed, do not constitute an unreviewed safety question as I defined in 10 CFR 50.59. That is, they: Jl
- 1. will not increase the probability or consequences of an accident or' malfunction of equipment important to safety as previously evaluated in the Safety Analysis j
r Report; i
- 2. will not create the possibility of an accident or malfunction of a type different l from any previously evaluated in the Safety Analysis Report; and j
- 3. will not reduce the margin of safety as defined in the basis for any technical :
specification.
{
The changes involve no significant hazards consideration, as defined in i 10 CFR 50.92. ,
VII. REFERENCES -
- 1. American Society for Testing and Materials, ASTM D 270-65 " Sampling Pettoleum and Pettoleum Products."
Attachment il to JPN-93-083 SAFETY EVALUATION Page 4 of 4
- 2. James A. FitzPatrick Nuclear Power Plant Process Surveillance Procedure PSP-7,
" Diesel Fuel Oil Sampling and Analysis," Revision 8, dated September 5,1991.
- 3. American Society for Testing and Materials, ASTM D 4057-88 " Manual Sampling of Petroleum and Petroleum Products."
- 4. American Society for Testing and Materials, ASTM D 975-81 " Standard Specifications for Diesel Fuel Oils."
- 5. NUREG-1433 " Standard Technical Specifications for General Electric Boiling Water Reactors (BWR/4)," Revision 0, dated September 1992.
- 6. American Society for Testing and Materials, ASTM D 975-92 " Standard Specifications for Diesel Fuel Oils."
- 7. James A. FitzPatrick Nuclear Power Plant Updated Final Safety Analysis Report Section 9.8.4 " Inspection and Testing," through Revision 5, dated January 1993.
- 8. James A. FitzPatrick Nuclear Power Plant Safety Evaluation Report (SER), dated November 20,1972, and Supplements.
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Attachment lit to JPN-93-083
' PROPOSED TECHNICAL SPECIFICATION CHANGE - -
DIESEL FUEL OIL SAMPLING CLARIFICATION ,
MARKUP OF TECHNICAL SPECIFICATION PAGE l
(JPTS-93-001) l i
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New York Power Authority 1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT-Docket No. 50-333 - :
DPR-59 !
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JAFNPP t .
l ' A. Hiah Pressure Water Fire Protection System (Cont'd) A. Hiah Pressure Water Fire Protection System (Cont'd)
- 3. If 1. above cannot be fulfilled, place the reactor in Hot jlam Freauency Standby within six (G) hours and in Cold Stmtdown within the following thirty (30) hours. h. Fire pump diesel engine Once/ Month by verifying the fuel storage tank contains at least 172 gallons of fuel.
- i. Diesel fuel from each o Once/Ouarter ta tained in accordance with)
ASTM.n>7n fi5)is within the acceptable limits for quality as per the following:
Flash Point *F 125'F min.
Pour Point 'F 10*F max.
Water & Sediment 0.05% max.
Ash 0.01 % max.
Distillatico 90% Point 540 min.
Viscosity (SSU) @ 100*F 40 max.
Sulfur 1% max.
Copper Strip Corrosion No. 3 max.
Cetane # 35 min.
- j. Fire pump diesel engine Once/18 months by inspection during shut down in accordance with procedures prepared in conjunction with manufacturers recommendations and verifying the diesel, starts from ambient conditions on the auto start signal and operates for 2 20 minutes while loaded with the fire pump.-
Amendment No. p. If4,190 244c
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