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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20212G1611999-09-22022 September 1999 Proposed Tech Specs,Requesting one-time Extension of Unit 2 Surveillance Interval for Snubber Functional Testing ML20212F6611999-09-20020 September 1999 Proposed Tech Specs,Revising Surveillance Std to Which Ventilation Charcoal Must Be Laboratory Tested as Recommended by GL 99-02 ML20210B8981999-07-15015 July 1999 Final Typed Pages for LARs 109 & 115,previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115 ML20210B8771999-07-15015 July 1999 Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by ML20210B8401999-07-15015 July 1999 Proposed Tech Specs Revising Surveillance Frequency for Quench & Recirculation Spray Systems Nozzle Air Flow Test from 5 Years to 10 Years,Per Guidance Provided in GL 93-05 ML20209C1941999-06-28028 June 1999 Typed,Final TS Pages for LAR 115.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196G3871999-06-22022 June 1999 Proposed Final Tech Spec Pages for LARs 259 & 131 ML20196F6881999-06-17017 June 1999 Proposed Tech Specs Updating Heatup,Cooldown & Overpressure Protection Curves & Bases to Apply for Up to 15 EFPYs ML20196F0191999-06-17017 June 1999 Proposed Tech Specs Pages for LARs 262 & 135 ML20195K1821999-06-15015 June 1999 Proposed Tech Specs Pages for LAR 109 Re RCS ML20207E1851999-05-27027 May 1999 Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing ML20207E2331999-05-27027 May 1999 Proposed Tech Specs 3/4.3.3.3,relocating Seismic Instrumentation Requirements to Licensing Requirements Manual Based on Guidance Provided in GL 95-10 ML20207E2081999-05-27027 May 1999 Proposed Revised Tech Specs for LARs 259 & 131,revising Qualifications for Operations Mgt & Incorporating Generic Position Titles ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 1999 Proposed Tech Specs Re Limiting Safety Sys Settings 2.2.1 & Associated Table 2.2-1 ML20206N9541998-12-24024 December 1998 Proposed Tech Specs,Modifying Applicable Sections by Removing Rod Position Deviation Monitor,Rod Insertion Limit Monitor,Afd Monitor & QPTR Monitor ML20198F9661998-12-24024 December 1998 Proposed Tech Specs Section 3/4.8.1, AC Sources, Clarifying EDG Fuel Oil Storage Requirements by Addition of Term Usable & Increasing EDG Largest Single Load Rejection Test Requirements ML20198D6711998-12-14014 December 1998 Proposed Typed,Final Tech Specs Pages for LARs 246 & 116, Consisting of Editorial Changes Due to Pagination,Changes Incorporated by Previous Amends & Corrected Typos ML20155J0161998-11-0303 November 1998 Proposed Tech Specs Page 3/4 1-15,re Reactivity Control Sys ML20155B9681998-10-23023 October 1998 Proposed Final,Typed Tech Specs Bases Pages for LARs 260 & 133 Re Limiting Safety Sys Settings ML20154Q8021998-10-15015 October 1998 Proposed Tech Specs,Deleting Two License Requirements, Modifying One LCO Applicability,Modifying Three Definitions, Changing Action Statement Number & Deleting Meteorological Monitoring Spec ML20154Q4341998-10-15015 October 1998 Proposed Tech Specs,Adding Discussion That Explains Why Use of Time Constants,Expressed as Equality,Such as T = X Seconds,Are Acceptable ML20154D6381998-09-30030 September 1998 Proposed Tech Specs Re Revised Typed Bases for LAR 235 ML20154C6501998-09-24024 September 1998 Proposed Tech Specs Section 3.1.2.8,eliminating Potential for non-conservative Interpretation of Values of RWST & Bat Min Contained Volume & Eliminating Need for Plant Administrative Controls ML20197C5711998-09-0808 September 1998 Proposed Typed,Final TS Pages Re Surveillance Requirements for LAR 235 ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20199J4391998-01-29029 January 1998 Proposed Tech Specs Re Radiological Doses for Locked Rotor Accident ML20198D4081997-12-19019 December 1997 Proposed Tech Specs,Modifying Neutron Flux Requirements to Allow Use of Alternate Detectors ML20198P6571997-11-0404 November 1997 Proposed Tech Specs Table 3.3-4 Re Emergency Bus Undervoltage Trip Setpoint,Allowable Valve & Time Delay for DG Start ML20212C8881997-10-22022 October 1997 Proposed Tech Specs 3.4.8,reducing RCS Specific Activity Limits Per GL 95-05 ML20217A9801997-09-11011 September 1997 Proposed Tech Specs Implementing line-item Improvements Provided in GL 93-08 for Removal of Response Times from TS ML20210L4381997-08-13013 August 1997 Proposed Tech Specs Revised Typed Pages for TS Change Requests 213 & 80,requiring Addl Revs from Pages Submitted in ML20141K5371997-05-23023 May 1997 Proposed Tech Specs Re Typed Paged for Change Request 213 & 80 ML20137C9111997-03-14014 March 1997 Proposed Tech Specs Re Administrative Controls Related to QA ML20147E6511997-03-10010 March 1997 Proposed Tech Specs Modifying Specification 3.4.5 to Allow SG Tube Sleeving Using Framatome Process ML20136G2091997-03-10010 March 1997 Proposed Tech Specs,Modifying Spec 3.4.5 to Allow SG Tube Sleeving Using CE Process ML20147E6301997-03-10010 March 1997 Proposed Tech Specs Modifying Unit 1 Design Feature Section 5.2.1 to Add ZIRLO as Fuel Assembly Matls & Adds Ref to NRC Approved WCAP-12610 to Administrative Control 6.9.1.12 for Both Units 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212G1611999-09-22022 September 1999 Proposed Tech Specs,Requesting one-time Extension of Unit 2 Surveillance Interval for Snubber Functional Testing ML20212F6611999-09-20020 September 1999 Proposed Tech Specs,Revising Surveillance Std to Which Ventilation Charcoal Must Be Laboratory Tested as Recommended by GL 99-02 ML20210B8771999-07-15015 July 1999 Final,Typed TS (Pages for LARs 262 & 135,previously Submitted with Editorial Changes Identified by ML20210B8981999-07-15015 July 1999 Final Typed Pages for LARs 109 & 115,previously Submitted by 990615 & 28 Ltrs.Revised Pages Replace Those Previously Provided for LARs 109 & 115 ML20210B8401999-07-15015 July 1999 Proposed Tech Specs Revising Surveillance Frequency for Quench & Recirculation Spray Systems Nozzle Air Flow Test from 5 Years to 10 Years,Per Guidance Provided in GL 93-05 ML20209C1941999-06-28028 June 1999 Typed,Final TS Pages for LAR 115.Summary Description of Editorial Changes Incorporated in Addition to Those Addressed in Previously Provided marked-up Pages ML20196G3871999-06-22022 June 1999 Proposed Final Tech Spec Pages for LARs 259 & 131 ML20196F0191999-06-17017 June 1999 Proposed Tech Specs Pages for LARs 262 & 135 ML20196F6881999-06-17017 June 1999 Proposed Tech Specs Updating Heatup,Cooldown & Overpressure Protection Curves & Bases to Apply for Up to 15 EFPYs ML20195K1821999-06-15015 June 1999 Proposed Tech Specs Pages for LAR 109 Re RCS ML20207E1851999-05-27027 May 1999 Proposed Tech Specs,Revising Frequency Notation for Manual Functions Specified in ESFAS to More Clearly Denote Appropriate Refueling Frequency for Testing ML20207E2331999-05-27027 May 1999 Proposed Tech Specs 3/4.3.3.3,relocating Seismic Instrumentation Requirements to Licensing Requirements Manual Based on Guidance Provided in GL 95-10 ML20207E2081999-05-27027 May 1999 Proposed Revised Tech Specs for LARs 259 & 131,revising Qualifications for Operations Mgt & Incorporating Generic Position Titles ML20205H5121999-03-31031 March 1999 Proposed Tech Specs Changes to Index Page Xvii,Changing Wording of Title for Table 3.7-1.Table 3.7-2 Will Be Changed to Be Consistent with Title of Table 3.7-3 ML20211N6651999-03-25025 March 1999 Issue 3,rev 3 to Bvps,Unit 1 Inservice Testing (IST) Program for Pumps & Valves ML20204E4381999-03-16016 March 1999 Proposed Tech Specs Bases Section 3/4.7.13,adding Wording Which Discusses Design Bases of Sys in Greater Depth ML20204E3851999-03-16016 March 1999 Proposed Tech Specs LCO 3.7.1.3,increasing Min Vol in Primary Plant DW to 127,500 Gallons,Adding New Footnote & Revising Wording Contained Action Statements ML20207K1331999-03-0303 March 1999 Proposed Tech Specs Changing Qualifications for Operations Mgt & Incorporating Generic Titles to Eliminate Need to Develop Amend Request When Corresponding plant-specific Titles Are Changed ML20207E6261999-02-26026 February 1999 Proposed Typed,Final Tech Specs Pages for LAR 111 ML20199G5431999-01-18018 January 1999 Proposed Tech Specs Re Limiting Safety Sys Settings 2.2.1 & Associated Table 2.2-1 ML20198F9661998-12-24024 December 1998 Proposed Tech Specs Section 3/4.8.1, AC Sources, Clarifying EDG Fuel Oil Storage Requirements by Addition of Term Usable & Increasing EDG Largest Single Load Rejection Test Requirements ML20206N9541998-12-24024 December 1998 Proposed Tech Specs,Modifying Applicable Sections by Removing Rod Position Deviation Monitor,Rod Insertion Limit Monitor,Afd Monitor & QPTR Monitor ML20198D6711998-12-14014 December 1998 Proposed Typed,Final Tech Specs Pages for LARs 246 & 116, Consisting of Editorial Changes Due to Pagination,Changes Incorporated by Previous Amends & Corrected Typos ML20205F6961998-11-30030 November 1998 Revs to Offsite Dose Calculation Manual ML20211K6871998-11-30030 November 1998 Issue 2,Rev 1 to Inservice Testing (IST) Program for Pumps & Valves ML20155J0161998-11-0303 November 1998 Proposed Tech Specs Page 3/4 1-15,re Reactivity Control Sys ML20155B9681998-10-23023 October 1998 Proposed Final,Typed Tech Specs Bases Pages for LARs 260 & 133 Re Limiting Safety Sys Settings ML20154Q8021998-10-15015 October 1998 Proposed Tech Specs,Deleting Two License Requirements, Modifying One LCO Applicability,Modifying Three Definitions, Changing Action Statement Number & Deleting Meteorological Monitoring Spec ML20154Q4341998-10-15015 October 1998 Proposed Tech Specs,Adding Discussion That Explains Why Use of Time Constants,Expressed as Equality,Such as T = X Seconds,Are Acceptable ML20154D6381998-09-30030 September 1998 Proposed Tech Specs Re Revised Typed Bases for LAR 235 ML20154C6501998-09-24024 September 1998 Proposed Tech Specs Section 3.1.2.8,eliminating Potential for non-conservative Interpretation of Values of RWST & Bat Min Contained Volume & Eliminating Need for Plant Administrative Controls ML20197C5711998-09-0808 September 1998 Proposed Typed,Final TS Pages Re Surveillance Requirements for LAR 235 ML20154D5241998-08-14014 August 1998 Issue 2,Rev 0C to Inservice Testing (IST) Program for Pumps & Valves ML20202G9831998-07-22022 July 1998 Issue 3,rev 2 to BVPS Unit 1 IST Program for Pumps & Valves ML20236S4921998-07-15015 July 1998 Proposed Tech Specs 3/4 3 Re Reactor Trip Sys & ESF Sys Instrumentation ML20236S2881998-07-13013 July 1998 Proposed Tech Specs Revising BVPS-1 UFSAR Pages 9.7-7 & 8 & BVPS-2 UFSAR Pages 3.6-11 & 12 Re Potential Flooding of Intake Structure Pump Cubicles ML20236P8051998-07-0909 July 1998 Proposed Tech Specs Revising TS 3.7.1.1, Svs, Incorporating Improved STS Guidance of NUREG-1431 & Recommendations of W Nuclear Safety Advisory 94-01,dtd 940120 ML20236P7761998-07-0909 July 1998 Proposed Tech Specs 3/4 3-2,3/4 3-11 & B 3/4 3-1b,modifying Source Range Neutron Flux Requirements to Allow Use of Alternate Detectors ML20249C4531998-06-23023 June 1998 Final Tech Specs Pages for LARs 256/126 ML20249C3161998-06-19019 June 1998 Proposed Tech Specs Modifying Channel Calibr Definition to Exclude RTDs & Thermocouples from TS Channel Calibr Requirements ML20248M1901998-05-19019 May 1998 Proposed Rev 2F to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves ML20247L3071998-05-14014 May 1998 Proposed Tech Specs,Final Pages for License Amend Requests 249/118 & 254/123,as Amends A-249,A-118,A-254 & A-123, Respectively ML20247J2851998-04-20020 April 1998 Alternative Request BV1-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (RC-R-1-C-8) ML20247J6761998-04-20020 April 1998 Alternative Request BV2-RV-AUG-1,Rev 1 for Reactor Vessel Lower Circumferential Weld (2RCS-REV21-C-4) ML20216J9771998-04-13013 April 1998 BVPS Unit 1,Cycle 13 Startup Physics Test Rept ML20248K3061998-03-20020 March 1998 Rev 1,Issue 3 to Inservice Testing Program for Pumps & Valves ML20237B9721998-03-19019 March 1998 Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees ML20216G7011998-03-17017 March 1998 Proposed Tech Specs,Revising Engineered Safety Feature Actuation Sys Instrumentation Table 3.3-3,action 34 & Associated Bases Section ML20216G1011998-03-16016 March 1998 Proposed Tech Specs Adding New LCO 3.0.6 to Section 3/4.0, Applicability ML20216G0801998-03-16016 March 1998 Proposed Tech Specs,Exempting Neutron Flux Detectors from Channel Calibr Requirements 1999-09-22
[Table view] |
Text
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REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:
- a. 1 1.0pci/ gram DOSE EQUIVALENT I-131, and
- b. I 100/5 pCi/ gram.
APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION MODES 1, 2, and 3*
l
- a. With the specific activity of the primary coolant >1.0 l pCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with T avg
<500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,
- b. With the specific activity of the primary coolant > 100/5 l pCi/ gram, be in HOT STANDBY with Tavg < 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1, 2, 3, 4 and 5
- a. With the specific activity of the primary _ coolant > 1.0 pCi/ gram DOSE EQUIVALENT I-131 or > 100/E pCi/ gram, perform the sampling and analysis requirement of item 4a of Table 4.4-12 until the specific activity of the primary coolant is restored to within its limits.
SURVEILLANCE REQUIREMENTS 4.4.8 -The specific activity of the primary coolant shall be determined to be within the limits be performance of the sampling and analysis program of Table 4.4-12.
1 hoh kDO $4 P
- With Tavg 1 500*F BEAVER VALLEY - UNIT 1 3/4 4-18 (next page is 3/4 4-20)
PROPOSED WORDING
. REACTOR COOLANT SYSTEM BASES The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity
> 1.0 pCi/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
Operation with specific activity levels exceeding 1.0 pCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limits shown on Figure 3.4-1 must be restricted since the activity levels allowed by Figure 3.4-1 increase the 2-hour thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.
Reducing T to <500*F prevents the release of activity should a steam avheneratortuberupturesincethesaturationpressure of the primary coolant is below the lift pressure of the atmospheric steam relief valves. The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action. Information obtained on iodine spiking will be used to assess the parameters associated with spiking phenomena. A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations. The various categories of load cycles used for design purposes are provided in Section 4.1.4 of the~FSAR. During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.
During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at the outer wall. These thermal-induced compressive streses tend to alleviate the tensile stresses induced by the internal pressure. Therefore, a pressure-temperature curve based on steady state conditions (i.e., no _ thermal stresses) represents a lower bound of all similar curves for finite heatup rates when the inner wall of the vessel is treated as the governing location.
BEAVER VALLEY - UNIT 1 B 3/4 4-5 PROPOSED WORDING
ADMINISTRATIVE CONTROLS ANNUAL REPORTS 1 6.9.1.4' Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior. to March 1 of each year. The 'intitial report shall be submitted prior to March 1 of the year following intitial criticality.
6.9.1.5 Reports required on an annual basis shall include:
- a. A tabulation of the number of station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according to work and job functions 2 (e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, 'and refueling). The dose assignments to various duty-functions may be estimated based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20 percent of the individual total dose need not be acounted for. In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
- b. Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or pressurizer safety valves.
- c. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.8. The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the'first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after. the radiciodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radioiodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit' was . exceeded; (4) Graph of the I-131 concentration and one other radiciodine -isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
1 A single submittal may be made for a multiple unit' site.
The submittal should combine those sections that are commmon to all units at the site.
2 This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.
BEAVER VALLEY - UNIT 1 6-14 PROPOSED WORDING
. ADMINISTRATIVE CONTROLS
- a. . ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- b. Inoperable seismic Monitoring Instrumentation ,
Specification 3.3.3.3.
- c. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
- d. Seismic event analysis, Specification 4.3.3.3.2.
- e. Sealed source leakage in excess of limits, Specification 4.7.9.1.3.
f.- Fire Detection Instrumentation, Specification 3.3.3.6.
- g. Fire Suppression Systems, Specifications 3.7.14.1, 3.7.14.2 and 3.7.14.3'and 3.7.14.5.
- h. Miscellaneous reporting requirements specified in the Action Statements for Radiological Effluent Technical Specifications.
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- i. Containment Inspection Report, Specification 4.6.1.6.2.
6.10 RECORD RETENTION 6.10.l' The following records shall be retained for at least five (5) years:
- a. Records and logs of facility operation covering time interval at each power level.
- b. Records and logs of principal maintenance activities,
'inspec.tions , repair and replacement of principal items of equipment related to nuclear safety.
- c. All REPORTABLE EVENTS.
- d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
- e. Records of reactor tests and experiments.
- f. Records of changes made to Operating Procedures.
- g. Records of radioactive shipments.
h.- Records of sealed source leak tests and results.
- i. Records of annual physical inventory of all sealed source material of record.
BEAVER VALLEY - UNIT 1 6-23 PROPOSED WORDING
ATTACHMENT B No Significant Hazard Determination Proposed Change Request No. 119 amends the Beavor Valley Power Station, . Unit No. 1 Technical _ Specifications to revise the reporting requirements on RCS specific- activity- from a special report to an annual report in accordance with Generic Letter 85-19.
Description of amendment. request: As part of the continuing effort to delet'e unnecessary reporting requirments, the NRC has determined that the reporting requirements for iodine spiking can be reduced from' a short-term report (Special Report or Licensee Event Report) .to an item to be included in the Annual Report. The information proposed for inclusion in the Annual Report is similar to that' previously. required in- the Licensee Event Report but has been changed to more clearly designate inclusion of the specific. activity analysis results and to delete the information regarding fuel burnup by core region. The following revisions are proposed:
(1) delete Section 3.4.8 Mode 1, 2 and 3* Action statement (a) and the .Special Report specified in Mode 1, 2, 3, 4 and 5 Action statement (a).
(2) move surveillance requirement 4.4.8 from page_3/4 4-19 to page 3/4 4-18, delete page 3/4 4-19 and add a note to page_3/4 4-18 (next page is 3/4 4-20).
(3) acd item (c) to Administrative Control 6.9.1.5 to include the results of specific activity analysis when the primary.. coolant exceeds the limits of Specification 3.4.8 in the Annual Report.
(4) revise Bases-3/4.4.8 to' reflect the new Action statements of Section 3.4.8.
'(5) . delete- Administrative Control 6.9.2.1 to- reflect the change in reporting requirements from Special Report to
~
Annual Report.
Basis for no significant hazard consideration determination:
This change is considered to be administrative in nature since the change reflects an NRC effort to eliminate unnecessary technical speci.fication requirements (Generic Letter 85-19). .. The NRC has determined that existing requirements to shutdown a plant if coolant iodine activity limits are exceeded for 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12-month period can be eliminated. For Beaver Valley, this is specified as 10
, . percent of the units total yearly operating time.
Based on the criteria for defining no significant hazards consideration setforth. in 10 CFR 50.92(c), plant operation in accordance with.the proposed amendment would not: -
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l m
, Attcchment B Page 2.
(1)' -involve a significant increase in the probability of occurrence or the- consequences of an accident or malfunction. of equipment important to safety previously eva'luated. The proposed changes do not involve physical change. to any plant safety.related systems, components or structures. The NRC has' determined that the reporting requirements for iodine spiking can be reduced from a short-term' (Special . Report or Licensee Event Report) to an~. item included in the Annual Report. The information
. proposed for inclusion in the Annual Report is similar-to that previously required in an LER but has been changed
.to' more clearly designate inclusion of the specific activity analysis results and to delete the information regarding fuel burnup by core' region.
The NRC has recognized the fact that the quality of nuclear fuel has greatly improved over the past decade which- results. in normal coolant iodine activity well Lbelow the limit. In addition,'10 CFR 50.72(b)(1)(ii) requires immediate NRC notification of fuel cladding
' failures .that exceed expected values or that are caused by unexpected factors. 'Therefore, the NRC considers this technical specification' limit no lenger necessary on the basis. that proper fuel management and existing reporting requirements should preclude ever approaching the limit.
Based on the above, the. proposed. changes are administrative in nature since the reporting methods have been revised and the coolant activity limit remains unchanged. These changes do not affect ~the accident analyses, therefore, the probability of an occurrence or consequence of an accident or malfunction of. equipment previously evaluated will not be increased.
(2) create the probability for an accident or malfunction of a different type than previously evaluated since no change in plant operations or to equipment or components is required. The changes revise the RCS specific activity reporting requirements from a special report to an annual report in accordance with Generic Letter 85-19.
(3) involve ~a significant reduction in the margin of_ safety since the change in reporting requirements are administrative in nature and do not affect the safe operation of the plant. The technical specification limits remain unchanged and the bases have been revised to reflect the change in Action statements as recommended by the NRC.
These changes do 'not ~ involve any physical changes to plant safety related systems, components or structures, will not increase the likelihood of a malfanction of safety related equipment, increase the consequences of an accident previously analyzed, nor create the possibility of a malfunction different than previously evaluated.
Therefore, based on the above, it is proposed to characterize the change as involving a no significant hazards consideration.
t