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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability ML20078A7731994-06-24024 June 1994 Proposed Tech Specs Reflecting Removal of Recirculation Flow Scram ML20069M8231994-06-15015 June 1994 Proposed Tech Spec 2.3.D, Reactor High Pressure,Relief Valve Initiation ML20070R5261994-05-12012 May 1994 Proposed TS Sections 3.1 & 4.1 for Protective Instrumentation ML20029E0451994-05-0606 May 1994 Proposed Tech Specs Clarifying Requirements for Demonstrating Shutdown Margin ML20065M9991994-04-19019 April 1994 Proposed Tech Specs Updating & Clarifying TS 3.4.B.1 to Be Consistent W/Existing TS 1.39 & 4.3.D Re Five Electromatic Relief Valves Pressure Relief Function Inoperable or Bypassed During Sys Pressure Testing ML20029C7571994-04-15015 April 1994 Proposed TS Change Request 215,deleting Audit Program Frequency Requirements from TS 6.5.3 & Utilize Operational QA Plan as Controlling Document 1999-07-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212B5741999-09-0505 September 1999 Rev 11 to 2000-ADM-4532.04, Oyster Creek Emergency Offsite Dose Calculation Manual ML20209H5051999-07-14014 July 1999 Proposed Tech Specs Pages 3.1-15 & 3.1-17 of Table 3.1.1 ML20209E0951999-07-0707 July 1999 Proposed Tech Specs,Changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20212H5441999-06-18018 June 1999 Proposed Tech Specs Reflecting Installation of Addl SFP Storage Racks That Will Accommodate Increase in Spent Fuel Assemblies Beyond Existing Storage Capacity of SFP as Described in Licensing Rept ML20195D0761999-06-0303 June 1999 Proposed Tech Specs,Permitting Plant Operation with Three Operable Recirculation Loops ML20205P8531999-04-15015 April 1999 Proposed Tech Specs,Modifying Number of Items in Sections 2 & 3 of Tss,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4 ML20198K0671998-12-23023 December 1998 Proposed Tech Specs Pages 3.8-2 & 4.8-1,changed to Specify Surveillance Frequency of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish That Existing SLMCPR Contained in TS 2.1.A Is Applicable for Next Operating Cycle (Cycle 17) ML20236T4811998-07-21021 July 1998 Proposed Tech Specs Re Changes to Administrative Controls ML20236T4981998-07-21021 July 1998 Proposed Tech Specs Re Reactivity Control ML20236J1431998-06-30030 June 1998 Proposed Tech Specs,Consisting of Revised Page 3-5 Re RPV Pressure/Temp Limits ML20236H2181998-06-29029 June 1998 Proposed Tech Specs,Modifying EDG Insp Requirement Previously Submitted in Entirety ML20248K2851998-05-28028 May 1998 Proposed Tech Specs Re That Such First Type a Test Required by Primary Containment Leakage Rate Testing Program Be Performed During Refueling Outage 18R ML20197G2771997-12-23023 December 1997 Proposed Tech Specs Reflecting Change in Trade Name of Owner & Operator of Oyster Creek Nuclear Generating Station ML20197J2561997-12-10010 December 1997 Proposed Tech Specs Changing Pages 2.3-6,2.3-7,3.1-11, 3.1-14,3.1-16,3.4-8,3.8-2,3.8-3,4.3-1,4.5-13 & 6-1 ML20210L3311997-08-15015 August 1997 Proposed Tech Specs,Incorporating Note Which Indicates That Proposed Change to SL Mcrp Applicable for Current Operating Cycle (Cycle 16) Only ML20135C2001996-11-27027 November 1996 Proposed Tech Specs Pages 4.7-1,4.7-2,4.7-3 & 4.7-4 Re Surveillances for Station Batteries ML20129K3401996-11-12012 November 1996 Proposed Tech Specs,Consisting of Change Request 224, Implementing Revised 10CFR20, Stds for Protection Against Radiation Effective 910620 ML20134H0541996-10-31031 October 1996 Proposed Tech Spec,Requesting Deletion of Table 3.5.2 ML20129C0691996-10-10010 October 1996 Proposed Tech Specs,Clarifying Functional Requirement to Provide Interlock Permissive Which Ensures Source of Cooling Water Available Via Core Spray Sys Prior to Depressurization ML20129A5731996-10-10010 October 1996 Proposed Tech Specs,Revising Addl Group of Surveillances Where Justification Completed Following Receipt of Amend 144 ML20134F4101996-10-0404 October 1996 Proposed Tech Specs 2.1.A & 3.10.C to Reflect Change in SLMCPR & Revise Operating CPR Limit for Stability, Respectively ML20117E7061996-08-23023 August 1996 Proposed Tech Specs,Proposing New pressure-temp Limits Up to 22,27 & 32 EFPY Based on Predicted Nilductility Adjusted Ref Temp for Corrresponding EFPY of Operation ML20115G2101996-07-17017 July 1996 Proposed Tech Specs,Allowing Implementation of 10CFR,App J, Option B ML20113A8641996-06-19019 June 1996 Proposed Tech Specs Table of Contents,1.24 Re Footnote to definition,1.25 Re Definition,Section 3.5.A.3b Re Containment,Section 4.5 Re Containment,Bases for Section 4.5 & Section 6.9.3.b Re Reporting Requirements ML20111A3841996-05-0707 May 1996 Proposed Tech Specs,Adopting Provisions of STS NUREG-1433, Rev 1,dtd 950407,Sections SR 3.0.1,3.0.3 & Associated Bases ML20107E7751996-04-15015 April 1996 Proposed Tech Specs 5.3.1 Re Handling Heavy Loads Over Irradiated Fuel ML20101P1561996-03-31031 March 1996 Rev 9 to Oyster Creek Nuclear Generating Station Pump & Valve IST Program ML20101J7681996-03-28028 March 1996 Proposed Tech Specs,Modifying Statements in TS & Bases to Correctly Reflect Ref Parameter for Anticipatory Scram Signal Bypass ML20101J6091996-03-25025 March 1996 Proposed Tech Specs,Deleting Spec Which Requires Thorough Insp of EDG Every 24 Months During Shutdown ML20100J9151996-02-23023 February 1996 Proposed Tech Specs Re Implementation of 10CFR50,App J, Option B ML20100H9971996-02-22022 February 1996 Proposed Tech Specs 3.7-1,3.7-2,4.7-1 & 4.7-2 Re Deletion of TS Requirement to bi-annually Inspect EDG & Mod of Spec Re AOT ML20095C1031995-12-0505 December 1995 Proposed Tech Specs Re Rev of Submittal Date for Annual Exposure Data Rept Bringing Plant Into Conformance w/10CFR20.2206 & Relaxing Overly Restrictive Administrative Requirement ML20086A7161995-06-26026 June 1995 Proposed Tech Specs Re Performance of Reactor Shutdown & Drywell to Inspect Snubbers in Svc for Only 12 Months ML20080P6501995-02-28028 February 1995 Proposed Tech Specs Change Request 225 Re Change to Page 6-4 of Tech Spec Section 6.5.1.12.Change Consistent w/NUREG-1433,STSs General Electric Plants,BWR/4,Rev 0,dtd 920928 ML20078N3791995-02-0808 February 1995 Proposed Tech Specs Re Oyster Creek Spent Fuel Pool Expansion ML20078Q6481994-12-15015 December 1994 Revised TS & Bases Pages to Section 3.1 of TS Change Request 191 ML20078M1431994-11-25025 November 1994 Proposed TS 5.3.1.E,allowing 2,645 Fuel Assemblies to Be Stored in Fuel Pool ML20073F9501994-09-26026 September 1994 Revised Plan for Long Range Planning Program for Oyster Creek Nuclear Generating Station ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20072S2921994-09-0202 September 1994 Proposed Tech Specs Supporting Rev of APRM Channel Calibr Interval from Weekly to Quarterly ML20072Q4251994-08-20020 August 1994 Rev 0 to Oyster Creek Nuclear Generating Station Sea Turtle Surveillance,Handling & Reporting Instructions for Operations Personnel ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability 1999-09-05
[Table view] |
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4.5-fa P. Suppression Chamber Surveillance
- 1. At least once per day the suppression chamber water level and temperature and pressure suppression system pressure snall oe checked.
- 2. A visual inspection of the suppression cnamDer interior, including water line regions, shall be made at each major refueling outage.
- 3. Whenever heat from relief valve operation is being added to the suppression pool, the pool temperature shall be continually monitored and also observed until the heat addition is terminated.
- 4. Whenever operation of a relief valve is indicated,and the suppression pool temperature reaches 160*F or above while tne reactor primary coolant system pressure is greater than 180 psig, an external visual examination of the suppression chamber snall be made before resuming normal power operation.
1 l
Amendment No. 18, 32, 87 l
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4.5-6a-1 Q. Shock Suppressors (Snubbers)
- 1. Each snubber shall be demonstrated operaole by perforiaance of tne fol- i lowing inspection program,
- a. Visual Inspections All snubbers shall be visually inspected in accordance with the fol-lowing schedule:
No. Inoperable Snubbers Subsequent Visual Per Inspection Period Inspection Period
1 12 months T 255 2 6 months T 255 3,4 124 days T 255 5,6,7 62 days T 25%
8 or more 31 days 1254
- The provisions of Tecnnical Specification 1.24 are not applicaole.
The required inspection interval shall not be lengthened more than one step at a time. Tne snuobers may be categorized into two groups: tnose access-ible and those inaccessible during reactor operation. Each group may be inspected independently in accordance witn the above senadule,
- b. Visual Inspection Acceptance Criteria Visual inspections snall verify (1) tnat there are no visible indications of damage or impaired OPERABILITY, (2) attachments to *ne foundation or sup-porting structure are secure, and (3) in those locations wnere snuober move-ment can oe manually induced without disconnecting the snubber, that the snuboer nas freedom of movement and is not frozen up. Snubbers nnicn appear inoperable as .3 result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that tne affected snubber is functionally tested in the as found condition and determined operable per Specification 4.5.Q.d or 4.5.Q.e as applicable and that tne cause for the rejection has been clearly established and remedied for that particular snubber.
- c. Functional Tests At least once eacn refueling cycle, a representative saiaple (10% of the total of each type of snubber in use in tne plant) shall be functionally tested either in place or in a or un test. For each snuober tnat does not meet the functional test acceptance criteria of Specification 4.5.Q.d or 4.5.Q.e, an additional 107, of tnat type of snuocer shall De functionally tested. As used in tnis specification, type of snubber shall mean snubbers of the same design and manufacturer, mecnanical or hydraulic.
Amendment No.18
~
4.5-6a-2 The representative sample selected for functional testing shall include tne various configurations, operating environments and tne range of size and capacity of snubbers. At least 25f, of the snubbers in the representative sdmple shall include snuDbers from the following tnree categories:
- 1. The first snubber away from eacn reactor vessel nozzle.
- 2. Snubbers witnin 5 feet of heavy equipment (valve, pump, motor, etc.).
- 3. SnuDoers within 10 feet of the discharge from a safety relief valve.
In addition to the regular sample, snubDers which failed the previous funC-tional test shall be retested during the next test period. If a spare snuo-ber has been installed in place of a failed snuocer, tnen botn tne failed (if it is repaired and installed in another position) and the replacement snubber snall be retested. Tne results from testing of tnese snucoers are not to be included for determining additional sampling requirements.
For any snuboer that fails to locxup or fails to move, i.e., frozen in place, the cause will be evaluated. If caused by manufacturer or design deficiency, actions shall De taken to ensure tnat all snuboers of the same design are not subject to the same defect.
- d. Hydraulic Snubbers functional Test Acceptance Criteria The hydraulic snubber functional test snall verify tnat-
- 1. Activation (restraining action) is achieved witnin the specified range of velocity or acceleration in botn tension and compression.
- 2. Snubber bleed, or release rate, wnere required, is within the speci-fied range in compression or tension. For snubbers specifically required to not displace under continuous load, the aoility of the snuDber to withstand loaa witnout displacement shall be verified,
- e. Mechanical Snubbers Functional Test Acceptance Criteria The mechanical snubber functional test shall verify taat:
1.
The force that initiates free movement of the snubber rod in either tension or compression is less than tne specified maximum drag force.
Amendment No.
4.5-6a-3
- 2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.
- 3. Snubber release rate, where required, is within the specified range in compression or tension. For snuobers specifically required not to displace under continuous load, the ability of the snuDDer to withstand load without displacement shall be verified,
- f. SnubDer Service Life Monitoring A record of the service life of each snuboer, the date at whicn the desig-nated service life commences and tne installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1.
Concurrent with the first inservice visual inspection and at least once per 18 months thereafter, the installation and maintenance records for each snubber shall De reviewed to verify that toe indicated service life nas not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to tne next scheduled snuboer service life review, the snubber service life shall be reevaluated or the snubber shall be replaced or reconditioned so as to extend its service life beyond the date of the next scheduled service life review. This reevaluation, replacement or reconditioning shall be in-dicated in the records. Service life shall not at any time affect reactor operations.
Amendment No.
4.5-9b of the system. Althougn this is basically a leak test, since the filters have charcoal of known efficiency and holding capacity for elemental iodine and/or methyl iodide, the test also gives an indication of the relative ef-ficiency of tne installed system. The test procedure is an adaptation of test procedures developed at the Savannan River Laboratory whicn were des-cribed in tne Ninth AEC Air Cleaning Conference
- High efficiency particulate filters are installed before and after the char-coal filters to minimize potential release of particulates to tne environ-ment and to prevent clogging of the iodine filters. An efficiency of 995 is adequate to retain particulates tnat may be released to the reactor building following an accident. This will be demonstrated by testing witn 00P as testing medium.
If laboratory tests for the adsorber material in one circuit of the Standby Gas Treatment System are unacceptable, all adsorber material in that circuit shall be replaced with adsorbent qualified according to Regulatory Guide 1.52. Any HEPA filters found defective shall be replaced with tnose quali-fled with Regulatory Position C.3.d of Regulatory Guide 1.62.
The snubber inspection frequency is based upon maintaining a constant level of snubber protection. Thus, the required inspection interval varies in-versely with the observed snubber failures. Tne number of inoperable snub-bers found during a required inspection deteruines tne time interval for tne next required inspection. Visual Inspections perfonned before an inspection interval has elapsed may be used as a new reference point to determine tne l
next inspection. However, tue results of such early inspections perfonned before the original required time interval has elapsed (nominal time less 257,) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
To furtner increase the assurance of snuober reliability, functional tests snould be performed at least once each refueling outage. Tnese tests will include stroking of the snubbers to verify proper piston movement, lock-up and oleed. Ten percent of tne snubbers represents an adequate sample for such tests. Observed failures of these samples require testing of additional units.
- 0. R. MunDaier, "In Place Hondestructive Leak Test for Iodine AdsorDers", Proceedings of tne Ninth AEC Air Cleaning Conference, USAEC Report CONF-660904,1966.
Amendment No. 18
6.10.2
,
- The following records snall b2 retained for th2 duration of tne Facility Operating License:
- a. Record and drawing changes reflecting facility design modifica- l tions made to systems and equipment described in tne Final Safety Analysis Report,
- b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
- c. Records of facility radiation and contamination surveys,
- d. Records of radiation exposure for all individuals entering radi-ation control areas,
- e. Records of gaseous and liquid radioactive material released to the environs,
- f. Records of transient or operational cycles for tnose facility components designed for a limited number of transients or cycles.
- g. Records of training and qualification for current members of the plant staff.
- h. Records of inservice inspections performed pursuant to tnese technical specificatons,
- i. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 tr'R 50.59.
- j. Records of reviews by the Independent Onsite Safety Review Group.
- k. Records for Environmental Qualification wnicn are covered under the provisions of paragraph 6.14.
- l. Records of tne service lives of all snuboers, including the date at which the service life connences, and associated installation and maintenance records.
6.10.3 Quality Assurance Records snall be retained as specified by the Quality Assurance Plan.
6.11 RADIATION PROTECTION PROGRAti Procedures for personnel radiation protection snall be prepared consistent witn tne requirements of 10 CFR 20 and shall De ap-proved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 (Deleted) 6-23 Amendment No. 69, 78