Letter Sequence Request |
|---|
TAC:42603, (Approved, Closed) TAC:42604, (Approved, Closed) TAC:51984, (Approved, Closed) TAC:51985, (Approved, Closed) TAC:53476, (Approved, Closed) TAC:53477, (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
Results
Other: ML19210D037, ML19248D525, ML19249B824, ML19254F785, ML19254F792, ML19256A718, ML19256A807, ML19256F452, ML19262B985, ML19275A926, ML19310A971, ML19352A969, ML20002A542, ML20008E032, ML20027E669, ML20027E675, ML20055A436, ML20062E590, ML20077Q266, ML20082H504, ML20107J281, ML20134G852, ML20138N067
|
MONTHYEARML18078A4061978-11-11011 November 1978 Forwards Comments in the Form of Redraft of Commission Paper Re Proposed Fed Register Notice Abnormal Occurrence Event, Loss of Containment Integrity W/Encl Draft Notice of Issuance Project stage: Draft Other IR 05000321/19780361978-11-29029 November 1978 IE Insp Repts 50-321/78-36 & 50-366/78-45 on 781106-09. Noncompliance Noted in Following Areas:Failure to Conduct Maint on safety-related Equipment & Failure to Submit a 30- Day Rept Project stage: Request ML20062E5901978-11-29029 November 1978 Discusses Possible Dangers of LOCA in Containment Purging During Normal Plant Oper.Requests Either Commitment to Limit Purging or Justification for Continuing.W/Encl ANO: 7812080207 Project stage: Other ML19256A7181979-01-0303 January 1979 Discusses Unlimited Purging Re Possible Failure of Automatic Isolation of Large Diameter Containment Purge Penetrations Used During Power Operations.Concludes That Bypass & Override Conditions Can Be Identified Project stage: Other ML19256A8071979-01-0909 January 1979 Responds to NRC .Review Underway Is Expected to Justify Unlimited Purging During Normal Plant Operation. Study to Be Completed by 790416 Project stage: Other ML19249B8241979-04-30030 April 1979 Summary of Review of Design of All Safety Actuation Signal Circuits Which Incorporate Manual Override Feature Project stage: Other ML19248D5251979-08-10010 August 1979 Responds to 790720 Request & Forwards Addl Info Re IE Bulletin 79-08.Standing Order Issued 790515 as Interim Means of Implementing Reporting Requirements of Item 9 of Bulletin Project stage: Other ML19249B8211979-08-29029 August 1979 Forwards Addl Response to 781129 Request for Info Re Vent & Purge Design & Operation.Rept Summary of Review of Design of All Safety Actuation Signal Circuits Which Incorporate Manual Override Feature Encl Project stage: Request ML19254B3631979-08-29029 August 1979 Forwards Request for Addl Info Re Override of Containment Purge Isolation Project stage: RAI ML19250A7591979-10-18018 October 1979 Forwards Response to 790913 Request for Commitment to Comply W/Requirements of NUREG-0578.Optimum Method of Addressing Concern,In Recognition of plant-unique Features, Proposed Project stage: Request ML19275A9261979-10-18018 October 1979 Forwards Commitment to Meet Requirements of NUREG-0578. Intends to Meet Requirements & Schedules Set Forth in NRC Project stage: Other ML19254F7851979-10-22022 October 1979 Requests Util Commitment to Comply W/Encl Interim Position Re Containment Purge & Vent Valve Operation Pending Resolution of Isolation Valve Operability.Commitment Needed within 45 Days Project stage: Other ML19254F7921979-10-30030 October 1979 Requests Util Commitment to Comply W/Encl Interim Position Re Containment Purge & Vent Valve Operation Pending Resolution of Isolation Valve Operability.Commitment Needed within 45 Days Project stage: Other ML19260B9881979-11-0606 November 1979 Forwards Request for Addl Info About Containment Purge & Vent Sys Re Util Plans for Unlimited Purging Project stage: RAI ML19210D0371979-11-13013 November 1979 Responds to NRC Re Containment Purging & Venting. Vent & Purge Valves at Three Units Qualify W/Nrc Guidelines to Extent Guidelines Apply Project stage: Other 05000321/LER-1979-081, Responds to 790927 Request for Expedited Implementation of Valve Qualification Program.Potential Problems Noted W/ Containment Purge & Vent Valves,Reported as LER 79-81.Valve Operator to Be Modified & Program Implemented1979-11-15015 November 1979 Responds to 790927 Request for Expedited Implementation of Valve Qualification Program.Potential Problems Noted W/ Containment Purge & Vent Valves,Reported as LER 79-81.Valve Operator to Be Modified & Program Implemented Project stage: Request ML19256F4521979-11-19019 November 1979 Forwards Addl Info Required for Completion of NRC Evolution of Electrical Override/Bypass Aspects of Containment Isolation Matter.Criteria Encl Project stage: Other ML19211A4411979-11-19019 November 1979 Forwards Request for Addl Info to Complete Evaluation of Electrical Override/Bypass Aspects of Containment Purge Sys Project stage: RAI ML19257A2931979-12-10010 December 1979 Forwards Request for Addl Info Re Util 790109 & 0829 Responses to NRC Re Containment Purging. Electrical Review Criteria Encl.Requests Reply within 60 Days Project stage: RAI ML19260C2221979-12-11011 December 1979 Forwards Criteria Re Electrical Override/Bypass for Use in Review of Operating Reactors.Maintaining Purge Valves Closed Does Not Resolve NRC Concern W/Purge Valve Circuitry Project stage: Approval ML19310A9711979-12-27027 December 1979 Requests Preliminary Evaluation of Licensee Response to NRC 791023 Interim Position for Containment Purge & Vent Valve Operation Pending Resolution of Isolation Valve Operability, Generic Item B-24.Evaluation Form Encl Project stage: Other ML19211C9021980-01-0909 January 1980 Submits Info in Response to NRC Requesting Commitment to Meeting Interim Position for Containment Purge & Vent Valve Operation. Interim Position Will Be Met Upon Completion of Bypass Line Wiring Mod Project stage: Meeting ML19262B9851980-01-16016 January 1980 Responds to NRC 791211 Request Re Containment Purge Sys & Engineered Safety Equipment Component Design.Sys Design & Procedures Utilized for Operation Provide Acceptable Degree of Safety Project stage: Other ML20055A4361980-02-28028 February 1980 Electrical,Instrumentation & Control Sys Support, Interim Rept Project stage: Other ML20008E0321980-10-0606 October 1980 Amend 61 to License DPR-65 Authorizing Cycle 4 Operation at 2,700 Mwt W/Mixed Core w/one-third Westinghouse Fuel & two- Thirds CE Fuel & Modified Guide Tubes for Control Element Assemblies Project stage: Other ML20002A5421980-11-0404 November 1980 Confirms Util Commitments to Interim Position on Containment Purging & Venting,Pending Resolution of Isolation Valve Operability.Commitment Will Remain in Effect Pending NRC long-term Review Project stage: Other ML19352A9691981-05-21021 May 1981 Provides Summary of Valve Qualification Efforts Resulting from NRC 790927 Effort.Valve Vendor Analysis Verified That Valve Actuator Has Sufficient Torque Capability to Overcome Forces That Resist Closure Subsequent to Design Basis LOCA Project stage: Other ML20027E6751982-10-0101 October 1982 Submits Info Re Status of Containment Purge & Vent Sys,In Response to NRC .Design Acceptable Since Weather at Plant Site Cannot Be Termed Severe Project stage: Other ML20027E6691982-11-0909 November 1982 Forwards Re Status of Containment Purge & Vent Sys.Original Submittal Apparently Never Received by NRC Project stage: Other ML20070E4031982-12-13013 December 1982 Advises That Specific Containment & Purge Valves Identified in NRC Are Not Applicable to Facilities.Meeting Requested to Determine Status of Remaining Issue Re Purging & Venting Project stage: Meeting ML20028C6081983-01-0606 January 1983 Notification of 830119 Meeting W/Util & Bechtel in Bethesda, MD to Discuss Status of Remaining Issues Re Review of Purging & Venting During Normal Operations Project stage: Meeting A03035, Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment1983-03-28028 March 1983 Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment Project stage: Request ML20071P0991983-05-31031 May 1983 Application for Amend to Licenses DPR-57 & NPF-5,revising Dose Equivalent Iodine Tech Specs to Reflect Current Requirements.Info Resolving Outstanding Purge & Vent Valve Operability Issues Encl Project stage: Request ML20071P1221983-05-31031 May 1983 Proposed Changes to Dose Equivalent Iodine Tech Specs & Preliminary Proposed Tech Specs for Drywell & Suppression Chamber Purge Sys Project stage: Request ML20024A6511983-06-15015 June 1983 Proposed Changes to Tech Specs 3/4.6-2,B 3/4 6-6 & Added 3/4.6-46 for Unit 2 & 3.7-10a,3.7-34,3.7-34a & Adding 3.7-10b & 3.7-34b for Unit 1 Re Purge & Vent Valve Operability Project stage: Request ML20024A6451983-06-15015 June 1983 Application for Amend to Licenses DPR-57 & NPF-5 Changing Tech Specs 3/4.6-2,B 3/4 6-6 & Adding 3/4.6-46 for Unit 2 & 3.7-10a,3.7-34,3.7-34a & Adding 3.7-10b & 3.7-34b for Unit 1 Re Purge & Vent Valve Operability Project stage: Request ML20077Q2661983-09-0101 September 1983 Provides Addl 10CFR50.92 Justification for 830531 & 0615 Applications for Amends to Tech Specs Re Change in Dose Equivalent Iodine & Change in Purge Valve Operability Specs Project stage: Other ML20082H5041983-11-22022 November 1983 Proposed Tech Spec Changes Re Dose Equivalent Iodine in Reactor Coolant Sys Project stage: Other ML20082H4861983-11-22022 November 1983 Application for Amend to Licenses DPR-57 & NPF-5,changing Tech Specs Re Dose Equivalent Iodine in Reactor Coolant Sys. Original Amend Submitted on 830531.Class III License Amend Fee Encl Project stage: Request ML20107J2811985-02-0404 February 1985 Amends 106 & 44 to Licenses DPR-57 & NPF-5,respectively, Revising Tech Specs to Reduce Equilibrium Activity Concentration Limit for Reactor Coolant for Unit 1 & to Reduce Offgas Activity Release Rate for Unit 2 Project stage: Other ML20134G8381985-08-20020 August 1985 Application for Amends to Licenses DPR-57 & NPF-5,adding Surveillance Requirements for fast-acting Dampers in Standby Gas Treatment Sys Installed During Recent Refueling Outage Project stage: Request ML20134G8521985-08-20020 August 1985 Proposed Tech Specs,Adding Surveillance Requirements for fast-acting Dampers in Standby Gas Treatment Sys Installed During Recent Refueling Outage Project stage: Other ML20138N0751985-12-11011 December 1985 Safety Evaluation Supporting Amends 118 & 58 to Licenses DPR-57 & NPF-5,respectively Project stage: Approval ML20138N0671985-12-11011 December 1985 Amends 118 & 58 to Licenses DPR-57 & NPF-5,respectively, Revising Tech Specs to Eliminate Time Restriction on Opening Purge & Vent Isolation Valves During Operating Modes 1,2 & 3 Project stage: Other 1980-01-16
[Table View] |
Similar Documents at Hatch |
|---|
|
Text
..
LIMITIto CONDITIONS FOR OPERATION SURVEILLANCE REQUIREENTS e
3.6.F Reactor Coolant Chemistry 4.6.F Reactor Coolant Chemistry
- 1. Radioactivity
- 1. Radioactivity Whenever the reactor is critical
- a. During equilibrium power the limits on activity concen-operation an isotopic trations in the reactor coolant analysis, including shall not exceed the equilibrium quantitative measurements value of 0.2 4 C1/gm of dose l
for at least I-131, I-132, equivalent
I-133, and I-135 shall be performed monthly on a If activity concentration
> 0.2 coolant liquid sample, p Ci/gm dose equivalent I-131 but
< 4.0 p C1/gm, operation may con-
- b. During equilibrium power tinue for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided operation an isotopic that operation under these condi-analysis, including tions shall not exceed 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> quantitative measurements in any consecutive 12 month period.
for at least Xe-133 and Xe-Should the total operating time of 135 shall be performed a specific activity > 0.2 p Ci/gm monthly on a steam jet air dose equivalent I-131 exceed 500 ejector off-gas sample.
hours in any consecutive 6 month period, the licensee shall report
- c. Additional coolant samples the number of hours of operation shall be taken whenever the above this limit to the NRC within reactor coolant dose equiva-30 days.
lent I-131 concentration exceeds 0.2 p Ci/gm and any I
of the following conditions If activity concentration > 0.2 are met:
p Ci/gm 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 con-
- 1) During startup tinuous time interval, or > 4.0 p C1/gm, be in at least HOT SHUT-
- 2) Following a power change DOWN with the main steam line exceeding 15% of rated l
isolation valves closed within 12 thermal power in less l
hours.
than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (net change averaged for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />).
- That I-131 concentration which alone would
- 3) The off-gas level, at produce the same thyroid dose as the the SJAE, increases by quantity and iodine mixture actually l
more than 10,000p C1/sec present.
In 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at release rate
< 80,000 p C1/sec, or
- 4) The off-gas level at the SJAE, increases by more than 15% in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at release rate > 75,000 pCi/sec.
- 5) Whenever the reactor coolant dose equivalent I-131 concentration ex-ceeds 4.0 p C1/gm.
l 3.6-4 8306070357 830531 i
PDR ADOCK 05000321 l
P PDR L
LIMITIMi CONDITIONS FOR OPERATION SURVEILLAKE REQUIREENTS Additional coolant liquid samples shall be taken at 4-hour intervals for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or until a
stable iodine concentra-tion below the limiting value of 4.0 4 C1/gm is established.
If the total iodine activity of the sample is below 0.2 4 C1/gm, an isotopic analysis to determine equivalent I-131 is not required.
All data obtained from normal and any addi-tional samples shall be included in the annual report.
If the limits of. the specification are exceeded, a report shall be made to the Direc-torate of Licensing within 30 days.
3.6-5
BASES FOR LIMITING CONDITIONS FOR OPERATION AND SURVEILLAPCE REQUIREENTS
- 3.6 Recirculation Pump Start The coolant in the bottom of the vessel is at a lower temperature than that in the upper regions of the vessel when there is not recirculation flow. The colder water is forced up when recirculation pumps are started.
This will not result in stresses which exceed ASE Boiler and Pressure Vessel Code,Section III limits when the temperature differential is not greater than 145 F.
F.
Reactor Coolant Chemistry The limitations on the specific activity of the primary coolant ensure that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> thyroid and whole body doses resulting from a main steam line failure outside the containment during steady state operation will not exceed small fractions of the dose guidelines of 10 CFR 100.
The values for the limits on specific activity represent interim limits based upon a parametric evaluation by the NRC of typical site locations.
These values are conservative in that specific site parameters, such as site boundary location and meteorological conditions, were not considered in this evaluation.
The maximum activity limit during a short term transient is established from consideration of a maximum iodine inhalation dose less than 300 rem.
The probability of a steam line break accident coincident with an iodine concentration transient is significantly lower than that of the accident alone, since operation of the reactor with iodine levels above the equilibrium value is limited to 10 percent of total operation.
Based upon a review of daily reactor water iodine concentrations at several sites that show the iodine transients during power generation are less than a factor of
- ten, sampling frequencies have been established that vary with the lodine concentration in order to assure that the maximum coolant iodine concentrations are not exceeded.
Materials in the primary system in contact with the coolant are primarily stainless steel and Zircaloy.
The reactor water chemistry limits are established to prevent damage to these materials.
Limits are placed on conductivity and chloride concentrations.
Conductivity is limited because it is continuously measured and gives an Indication of abnormal conditions and the presence of unusual materials in i
the coolant.
Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.
According to test data, allowable chloride concentrations could be set several orders of magnitude above the established limit at the oxygen concentration
(.2.3 ppm) experienced during power operation without causing significant failures.
Zircaloy does not exhibit similar stress corrosion failures.
However, there are some conditions under which the dissolved oxygen content of the reactor coolant water could be higher than.2.3 ppm, such as reactor starttp and hot standby.
During these periods, a more restrictive limit of 0.1 ppm has been established to assure that permissible chloride-oxygen combination are not l
exceeded.
During refueling when the reactor is depressurized Specification i
3.6.F.2.c would apply.
Boiling occurs at higher steaming rates causing deaeration of the reactor water, thus maintaining oxygen concentration at low levels and l
assuring that the chloride-oxygen content is not such as would tend to induce stress corrosion cracking.
3.6-18 l
ATTACHENT 5 CONTAIt4ENT SYSTEMS DRYWELL AND SUPPRESSION CHAMBER PURGE SYSTEM
'LIMITIPC C0tOITION FOR OPERATION 3.6.1.8 The drywell and suppression chamber 18 inch purge supply and exhaust isolation valves shall be OPERABLE and:
a.
Each valve may be open for purge system operation for inerting,-
deinerting and pressure control.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With an 18 inch drywell and suppression chamber purge supply and/or exhaust isolation valve (s) inoperable or open for other than inerting, deinerting or pressure control, close the open 18 inch valve (s) or otherwise isolate the penetration (s) within four hours or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.1.8.1 When not PURGING and VENTING, each 18 inch drywell and suppression chamber purge supply and exhaust isolation valve shall be verified to be:
a.
Closed at least monthly.
4.6.1.8.2. Once per operating cycle each 18 inch drywell and suppression chamber purge supply and exhaust isolation valve with resilient material seals shall be demonstrated OPERABLE by having its seal replaced and by verifying that the measured leakage rate is less than or equal to (0.01)
La when pressurized to P )-
a 3/4 6-11 l
i