|
|
(One intermediate revision by the same user not shown) |
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:REGULRY INFORMATION DISTRISUTI"SYSTEN (RIDE)ACCESSION NBR0 8505130355 DOC~DATE'f 85/05/07 NOTARIZED~NO FACILi50 400 Shearon Harr-fs Nuclear Powei" Plantr Unit ir Carolina AUTH, NAME AUTHOR AFFILIATION ZIMMERMANE S~R~Car ol{na Power L Light Co~RECIP~NAME<RECIPIENT AFFILIATION DENTONEH,R | | {{#Wiki_filter:REGULRY INFORMATION DISTRISUTI "SYSTEN (RIDE) |
| ~, Off fce of Nuclear'Reactor>>R'egulatfonr Dir actor>> | | ACCESSION NBR0 8505130355 DOC ~ DATE'f 85/05/07 NOTARIZED ~ NO DOCKET'. |
| | FACILi50 400 Shearon Harr-fs Nuclear Powei" Plantr Unit ir Carolina 05000400 AUTH, NAME AUTHOR AFFILIATION ZIMMERMANES ~ R ~ Car ol {na Power L Light Co ~ |
| | RECIP ~ NAME< RECIPIENT AFFILIATION DENTONEH,R ~, Off fce of Nuclear 'Reactor>> R'egulatfonr Dir actor>> |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Forwards addi{nfo re*fire protectfonrsueplement)ng 850019 submftta)r fn,resPonse to verbal r;equest'or clarificatfon from.Aux[1 fary Sys Branch revfe4ei Info covers>>alternate" shutdown sys, DISTRISUTION CODES SOOED COPIES'ECEIVED:LTR Q'NCL j SIZE: TITLE".Ld censing Submi t tal: Ff r e>>'Protection NOTES!DOCKET'.05000400 RECIPIENT ID CODE/NAME>>>> | | Forwards addi {nfo re* fire protectfonrsueplement)ng 850019 submftta)r fn,resPonse to verbal r;equest'or clarificatfon from. Aux[1 fary Sys Branch revfe4ei Info covers>> alternate" shutdown sys, DISTRISUTION CODES SOOED COPIES'ECEIVED:LTR Q'NCL TITLE". Ld censing Submi t tal: Ff r e>>'Protection j SIZE: |
| NRR>>L83>>BC INTERNAL!- | | NOTES! |
| ACRS 10 ELD/HDS1 NRR/DS I/AS 8 RGNEs COPIES" LTTR ENCL 1<<1 6 6 1-0 1 1 1~1 RECIPIENT'D CODE/NAME>> | | RECIPIENT COPIES" RECIPIENT'D COPIES ID CODE/NAME>>>> LTTR ENCL CODE/NAME>> LTVR ENCL NRR>> L83>> BC 1<<1 BUCKLEYEB 01 1 1 INTERNAL!- ACRS 10 6 6 ADM/LFMB 1 0 ELD/HDS1 1- 0 NRR/ . EB 06 p NRR/DS I/AS8 1 1 0$ 1 RGNEs 1 ~ |
| BUCKLEYEB 01 ADM/LFMB NRR/.EB 06 0$COPIES LTVR ENCL 1 1 1 0 p 1 EXTERNALS LPDR NSIC 03>>05>>1 1 1 1 NRC PDR 02'TOTAL NUMBER: OF COPIES'EQUIREDt LTTR 18 ENCL 16 l gL r P 1 Isv I L q frit t I 1<<1 hatt<<~C<<4 V<<0 a t l)1 r t it'I 1, ltt,&jl 1g a'll 1'<<S I Jl I v<<r1',,rl II V X II!~r>t I'11~)<<<<1 r<<<<$SV K S 1rjfrtl 1 tSII-'1<<tI IW<<r ll.tj g s'I I<<\f v 1rli<<11<<wt t f",11<<ii)f'1(<1~I.,'K, I"~t<<<<&~]f'I It s1 gjl, I ,'~,1 ,[sv II~v 7>i ll j , VK A 1 Ij ft", I K<<1'l f,~Q f,<<I'"<<c
| | 1 EXTERNALS LPDR 03>> 1 1 NRC PDR NSIC 05>> 1 1 02'TOTAL NUMBER: OF COPIES'EQUIREDt LTTR 18 ENCL 16 |
| @ME Carolina Power 8 Light Company qg Ov>Sa5 SERIAL: NLS-85-158 Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.1-DOCKET NO.50-000 FIRE PROTECTION
| |
|
| |
|
| ==Dear Mr.Denton:== | | l gL r I <<<<1 |
| Carolina Power R Light Company (CPRL)hereby submits additional information concerning fire protection at Shearon Harris Nuclear Power Plant.The enclosed information is submitted in response to a verbal request for clarification from the Auxiliary System Branch reviewer and supplements CPRL's April 19, 1985 submittal (NLS-85-132). | | ~ ) |
| If you have any questions concerning this material or require additional information, please contact me.Yours very truly, DCM/crs (1003DCM)Enclosure cc: Mr.B.C.Buckley (NRC)Mr.G.F.Maxwell (NRC-SHNPP) | | P 1 Isv I L q frit t I 1<<1 hatt<< |
| Dr.J.Nelson Grace (NRC-RII)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP) | | a t l)1 a'll 1 '<<S '11 r <<<<$ SV K r t IJl I v << |
| Wake County Public Library S.R Zi erman nager Nuclear Licensing Section Mr.Wells Eddleman Mr.John D.Runkle Dr.Richard D.Wilson Mr.G.O.Bright (ASLB)Dr.J.H.Carpenter (ASLB)Mr.J.L.Kelley (ASLB)8505130355 850507 PDR ADOCX 05000400 F PDR o>>411 Fayettevilte Street o P.O.8ox 1551 o Raleigh, N.C.27602 4
| | S |
| REACTOR SHUTDOWN BY USE OF THE ALTERNATIVE SHUTDOWN SYSTEM In general, recognizing the confined physical location of fires and the operational flexibility and physical diversity of systems available to achieve safe shutdown, one can assume that the plant's defense in depth fire protection features will limit fire damage to the extent that unaffected plant systems will be able to attain safe shutdown.An extensive effort would be required to identify the effects of postulated fires in potential plant locations on the plant systems which are normally available to support safe shutdown.As a conservative alternative to this approach, a minimum set of plant systems (safe shutdown systems)and components is identified in response to the requirements of 10 CFR 50 Appendix R.The identified systems and components can achieve and maintain safe shutdown regardless of the location of the fire and the loss of offsite power.Demonstration of adequate protection of this minimum set of systems from the effects of postulated fires constitutes an adequate and conservative demonstration of the ability to achieve and maintain safe shutdown for the purposes of fire protection. | | ~ C it r1 ',,rl II |
| | 'I 1, V X II! |
| | <<4 V <<0 ltt,& jl 1g ~r> t IW <<r ll.tj f ",11 ~t 1rjfrtl g s'I <<11<< wt << ii) f 1 tSII - ' 1<<tI I <<\ f v 1rli t '1( <1 |
| | ~ I.,'K, I" |
| | <<& ~ << ]f gjl, I |
| | , [sv II |
| | 'I It s1 ,'~,1 |
| | ~ v 7 , VK |
| | >i ll A Ij ", |
| | I'" |
| | ft I |
| | j 1 K |
| | <<1 |
| | 'l f, ~ <<c Q f, |
| | |
| | @ME Carolina Power 8 Light Company SERIAL: NLS-85-158 qg Ov >Sa5 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 - DOCKET NO. 50-000 FIRE PROTECTION |
| | |
| | ==Dear Mr. Denton:== |
| | |
| | Carolina Power R Light Company (CPRL) hereby submits additional information concerning fire protection at Shearon Harris Nuclear Power Plant. The enclosed information is submitted in response to a verbal request for clarification from the Auxiliary System Branch reviewer and supplements CPRL's April 19, 1985 submittal (NLS-85-132). |
| | If you have any questions concerning this material or require additional information, please contact me. |
| | Yours very truly, S. R Zi erman nager Nuclear Licensing Section DCM/crs (1003DCM) |
| | Enclosure cc: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. John D. Runkle Dr. J. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB) |
| | Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB) |
| | Wake County Public Library Mr. J. L. Kelley (ASLB) 8505130355 850507 PDR ADOCX 05000400 F PDR o>> |
| | 411 Fayettevilte Street o P. O. 8ox 1551 o Raleigh, N. C. 27602 |
| | |
| | 4 REACTOR SHUTDOWN BY USE OF THE ALTERNATIVESHUTDOWN SYSTEM In general, recognizing the confined physical location of fires and the operational flexibilityand physical diversity of systems available to achieve safe shutdown, one can assume that the plant's defense in depth fire protection features will limit fire damage to the extent that unaffected plant systems will be able to attain safe shutdown. An extensive effort would be required to identify the effects of postulated fires in potential plant locations on the plant systems which are normally available to support safe shutdown. As a conservative alternative to this approach, a minimum set of plant systems (safe shutdown systems) and components is identified in response to the requirements of 10 CFR 50 Appendix R. The identified systems and components can achieve and maintain safe shutdown regardless of the location of the fire and the loss of offsite power. Demonstration of adequate protection of this minimum set of systems from the effects of postulated fires constitutes an adequate and conservative demonstration of the ability to achieve and maintain safe shutdown for the purposes of fire protection. |
| The safe shutdown systems selected for SHNPP are capable of achieving and maintaining subcritical conditions in the reactor, maintaining reactor coolant inventory, maintaining reactor coolant pressure control, removing decay heat, achieving cold shutdown condition within 72 hours, and maintaining cold shutdown conditions thereafter. | | The safe shutdown systems selected for SHNPP are capable of achieving and maintaining subcritical conditions in the reactor, maintaining reactor coolant inventory, maintaining reactor coolant pressure control, removing decay heat, achieving cold shutdown condition within 72 hours, and maintaining cold shutdown conditions thereafter. |
| The following is a list and description of the specific shutdown functions necessary to satisfy the Alternative Shutdown System acceptance criteria: 1)Reactor Reactivity Control 2)Reactor Coolant System Inventory Control 3)Reactor Coolant Pressure Control 0)Reactor Heat Removal 5)Process Monitoring 6)Miscellaneous Supporting Functions As stated in our April 5, 1985 submittal in response to 010.05, the SHNPP design utilizes Alternative Shutdown following a fire induced evacuation of the Control Room.The SHNPP safe shutdown analysis assumes the reactor is tripped prior to control room evacuation. | | The following is a list and description of the specific shutdown functions necessary to satisfy the Alternative Shutdown System acceptance criteria: |
| This is consistant with the staff guidance provided in Generic Letter 85-01.The remaining operator actions required to take control of plant systems from the alternative shutdown system are carried out from fire zones unassociated with the control room.Ma'or E ui ment Available from Alternative Shutdown 1)Reactor Reactivity Control Reactor reactivity control is initially achieved by tripping the control rods into the core prior to control room evacuation. | | : 1) Reactor Reactivity Control |
| The reactor reactivity control function will provide sufficient shutdown margin to ensure that (1)the reactor can be made subcritical from required operating conditions, and (2)the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. | | : 2) Reactor Coolant System Inventory Control |
| (1443DCM/crs) | | : 3) Reactor Coolant Pressure Control |
| | : 0) Reactor Heat Removal |
| | : 5) Process Monitoring |
| | : 6) Miscellaneous Supporting Functions As stated in our April 5, 1985 submittal in response to 010.05, the SHNPP design utilizes Alternative Shutdown following a fire induced evacuation of the Control Room. The SHNPP safe shutdown analysis assumes the reactor is tripped prior to control room evacuation. This is consistant with the staff guidance provided in Generic Letter 85-01. |
| | The remaining operator actions required to take control of plant systems from the alternative shutdown system are carried out from fire zones unassociated with the control room. |
| | Ma'or E ui ment Available from Alternative Shutdown |
| | : 1) Reactor Reactivity Control Reactor reactivity control is initially achieved by tripping the control rods into the core prior to control room evacuation. The reactor reactivity control function will provide sufficient shutdown margin to ensure that (1) the reactor can be made subcritical from required operating conditions, and (2) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. |
| | (1443DCM/crs) |
| | |
| | The two means of reactivity control are: (I) control rods, which provide the immediate shut'down reactivity (initiated prior to control room evacuation), and (2) soluble boron addition to the RCS from the boric acid tank by the boric acid transfer pump (SB) and the charging/safety injection pump (SB). This will maintain adequate shutdown margin for the transition from Hot Standby to Cold Shutdown. |
| | No postulated fire will prevent the addition of soluble boron necessary to maintain required shutdown margin throughout the shutdown period. Available indication was provided in CPRL's April 5, 1985 response to 010.06. |
| | Reactor Coolant System Inventory Control The reactor coolant system inventory control function will ensure sufficient makeup inventory is provided for: |
| | o Reactor coolant system fluid losses due to reactor coolant system leakage, and o Shrinkage of the reactor coolant system water volume during cooldown from Hot Standby to Cold Shutdown conditions. |
| | Adequate performance of this function is assured by maintaining reactor coolant level within the pressurizer. |
| | Inventory makeup to the RCS will be from the boric acid tank by a charging path as described in I above. A back-up supply of borated water is available from the Refueling Water Storage Tank. The negative reactivity inserted by the control rods and boron addition will maintain the reactor core-subcritical with adequate Shutdown Margin while cooling down the RCS. |
| | Reactor Coolant Pressure Control Reactor coolant pressure control ensures that (l) reactor coolant system integrity is maintained by providing overpressure protection, and (2) sufficient subcooling margin is provided to minimize void formation within the reactor vessel. RCS pressure can be maintained by energization of the pressurizer heaters (SB power supply). Overpressure protection of the RCS is provided for in Hot Standby (prior to cooldown and depressurization) by the pressurizer safety valves. Depressurization capability is provided by the pressurizer power-operated relief valves (PORVs) (SB power supply). After depressurization, when the RCS is aligned with the Residual Heat Removal System (RHR), overpressure protection is provided by RHR suction relief valves. |
| | Adequate subcooled margin is achieved and maintained by operator action using pressure and temperature information received from the RCS pressure and temperature instrumentation. (Indication was provided in April 5 response to Olo.O6.) |
| | Reactor Heat Removal The reactor heat removal function is capable of transferring fission product decay heat from the reactor core at a rate such that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. Following a reactor trip with an assumed loss of offsite power, decay (14430'/crs ) |
| | |
| | ,heat is initially removed by natural circulation of the RCS, heat transfer to the main steam system through the steam generators, and operation of main steam PORVs (S/G AkC). Decay heat removal requires that sufficient feedwater be supplied to the steam generators to make up for the inventory discharged as steam by the main steam power-operated relief valves. The turbine driven auxiliary feedwater pump will supply sufficient feedwater to make up for'nventory losses during initial maintenance of Hot Standby and subsequent cooldown. Feedwater is available from the condensate storage tank, and alternatively from the emergency service water system. |
| | Hot standby can be maintained for 12 hours followed by 0 hours of cooldown to hot shutdown condition. Hot standby can be maintained beyond this 16-hour period by use of the Emergency Service Water System a back-up source of Auxiliary Feedwater water to the Condensate Storage Tank. |
| | After reduction of reactor coolant system temperature below 350'F, the RHR system (SB) is used (via valves 1RH-V 500 SB and 501 SA) to establish long-germ |
| | 'ore cooling through the removal of decay heat from the RCS through the |
| | , component cooling water system (SB) and the emergency service water system (SB). Assuming only 1 RHR heat exchanger I RHR pump are in service, cold shutdown can be achieved within 28 hours. |
| | : 5) Process Monitoring The process monitoring function is capable of providing readings of those plant process variables necessary for plant operators to perform and/or control the above identified functions. The available indicators were provided in CPRL's April 5, 1985 response to 010.06. |
| | : 6) Miscellaneous Support Functions The systems and equipment used to perform the functions described above in items 1-0 may require miscellaneous supporting functions. The major supporting functions are ac/dc power (D/G SB), Essential Services Chilled Water (SB), and HVAC to essential components (SB). These supporting functions will be available and capable of providing the support necessary to ensure acceptable performance of the previously identified safe shutdown features. |
| | (14430CH/crs ) |
|
| |
|
| The two means of reactivity control are: (I)control rods, which provide the immediate shut'down reactivity (initiated prior to control room evacuation), and (2)soluble boron addition to the RCS from the boric acid tank by the boric acid transfer pump (SB)and the charging/safety injection pump (SB).This will maintain adequate shutdown margin for the transition from Hot Standby to Cold Shutdown.No postulated fire will prevent the addition of soluble boron necessary to maintain required shutdown margin throughout the shutdown period.Available indication was provided in CPRL's April 5, 1985 response to 010.06.Reactor Coolant System Inventory Control The reactor coolant system inventory control function will ensure sufficient makeup inventory is provided for: o Reactor coolant system fluid losses due to reactor coolant system leakage, and o Shrinkage of the reactor coolant system water volume during cooldown from Hot Standby to Cold Shutdown conditions.
| | ~ ~ |
| 'Adequate performance of this function is assured by maintaining reactor coolant level within the pressurizer.
| | 4}} |
| Inventory makeup to the RCS will be from the boric acid tank by a charging path as described in I above.A back-up supply of borated water is available from the Refueling Water Storage Tank.The negative reactivity inserted by the control rods and boron addition will maintain the reactor core-subcritical with adequate Shutdown Margin while cooling down the RCS.Reactor Coolant Pressure Control Reactor coolant pressure control ensures that (l)reactor coolant system integrity is maintained by providing overpressure protection, and (2)sufficient subcooling margin is provided to minimize void formation within the reactor vessel.RCS pressure can be maintained by energization of the pressurizer heaters (SB power supply).Overpressure protection of the RCS is provided for in Hot Standby (prior to cooldown and depressurization) by the pressurizer safety valves.Depressurization capability is provided by the pressurizer power-operated relief valves (PORVs)(SB power supply).After depressurization, when the RCS is aligned with the Residual Heat Removal System (RHR), overpressure protection is provided by RHR suction relief valves.Adequate subcooled margin is achieved and maintained by operator action using pressure and temperature information received from the RCS pressure and temperature instrumentation.(Indication was provided in April 5 response to Olo.O6.)Reactor Heat Removal The reactor heat removal function is capable of transferring fission product decay heat from the reactor core at a rate such that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded.Following a reactor trip with an assumed loss of offsite power, decay (14430'/crs
| |
| )
| |
| ,heat is initially removed by natural circulation of the RCS, heat transfer to the main steam system through the steam generators, and operation of main steam PORVs (S/G AkC).Decay heat removal requires that sufficient feedwater be supplied to the steam generators to make up for the inventory discharged as steam by the main steam power-operated relief valves.The turbine driven auxiliary feedwater pump will supply sufficient feedwater to make up for'nventory losses during initial maintenance of Hot Standby and subsequent cooldown.Feedwater is available from the condensate storage tank, and alternatively from the emergency service water system.Hot standby can be maintained for 12 hours followed by 0 hours of cooldown to hot shutdown condition.
| |
| Hot standby can be maintained beyond this 16-hour period by use of the Emergency Service Water System a back-up source of Auxiliary Feedwater water to the Condensate Storage Tank.After reduction of reactor coolant system temperature below 350'F, the RHR system (SB)is used (via valves 1RH-V 500 SB and 501 SA)to establish long-germ'ore cooling through the removal of decay heat from the RCS through the , component cooling water system (SB)and the emergency service water system (SB).Assuming only 1 RHR heat exchanger I RHR pump are in service, cold shutdown can be achieved within 28 hours.5)Process Monitoring The process monitoring function is capable of providing readings of those plant process variables necessary for plant operators to perform and/or control the above identified functions.
| |
| The available indicators were provided in CPRL's April 5, 1985 response to 010.06.6)Miscellaneous Support Functions The systems and equipment used to perform the functions described above in items 1-0 may require miscellaneous supporting functions.
| |
| The major supporting functions are ac/dc power (D/G SB), Essential Services Chilled Water (SB), and HVAC to essential components (SB).These supporting functions will be available and capable of providing the support necessary to ensure acceptable performance of the previously identified safe shutdown features.(14430CH/crs
| |
| )
| |
| ~~4}} | |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20216G3501999-09-29029 September 1999 Confirms Conversations Re NRC Staff Voluntary Response to Orange County Discovery Requests.Staff Will Voluntarily Answer Discovery Requests & Will Not Waive Any Objection or Privilege Under NRC Regulations.Related Correspondence ML20212M1081999-09-29029 September 1999 Confirms Intent to Meet with Utils on 991025 in Atlanta,Ga to Discuss Pilot Plants,Shearon Harris & Sequoyah Any Observations & Lessons Learned & Recommendations Re Implementation of Pilot Program ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML20212H7741999-06-23023 June 1999 Responds to Re Petition Filed by Orange County Board of Commissioners Re Proposed Expansion of Sf Storage Capacity at Shearon Harris Npp.Public Meeting Will Be Held at Later Date.With Certificate of Svc.Served on 990624 ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML20206R2511999-05-19019 May 1999 Responds to Addressed to Chairman Jackson Requesting That NRC Grant Standing to Orange County Board of Commissioners in Shearon Harris Proceeding Currently Before Board.With Certificate of Svc.Served on 990519 ML20206Q5281999-05-17017 May 1999 Responds to 990304 Request for Two Rail Routes to Be Used for Transport of Spent Fuel from Brunswick Steam Electric Plant,Southport,Nc & Hb Robinson Steam Electric Plant, Hartsville,Sc to Shearon Harris Npp,Near New Hill,Sc ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9601999-05-11011 May 1999 Forwards Resolution Adopted by Carrboro Board of Aldermen at 990504 Meeting.Resolution Expresses Town Concern Re Util Plans to Double high-level Nuclear Waste Storage at Shnpp ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML20205M0431999-04-13013 April 1999 Eighth Partial Response to FOIA Request for Records.App Q & R Records Encl & Being Made Available in PDR ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl IR 05000400/19982011999-04-12012 April 1999 Discusses Safeguards Insp Rept 50-400/98-201 (Operational Safeguards Response Evaluation) on 980908-11.No Violations Noted.Licensee Performance During Evaluation Indicated Excellent Overall Contingency Response Capability 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18017A9241999-10-15015 October 1999 Provides Supplemental Info Re 981223 Lar,Placing Plant Spent Fuel Pools 'C' & 'D' in Service.Info Provided Does Not Change Util Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18017A9141999-10-12012 October 1999 Forwards Addl Info Re Second 10-year ISI Program Plan Relief Requests,As Requested During 990923 Telcon ML18017A9131999-10-0606 October 1999 Provides Notification That Three SROs Licensed at Shnpp Have Been Reassigned from Position for Which Util Previously Certified Need for SRO License.Name,Docket Number & License Number for Subject Sros,Encl.Encl Withheld ML18017A8911999-09-30030 September 1999 Submits Comment on Encl 2 to 990617 Memo Titled Summary of Meeting with Nuclear Energy Inst. Encl 2 Was Titled Draft Technical Study of Spent Fuel Pool Accidents for Decommissioning Plants. Rept Which Provides Info Encl Also ML20212J0741999-09-29029 September 1999 Refers to Proposed License Amend for Harris NPP Which Would Allow Licensee to Activate Two of Plant Spent Fuel Pools.Serves Copy of Orange County Second Set of Document Requests to NRC Staff,Dtd 990929.Related Correspondence ML18017A8941999-09-29029 September 1999 Forwards Response to NRC 990414 RAI Re GL 95-07, Pressure- Locking & Thermal-Binding of SR Power-Operated Gate Valves. ML18017A8881999-09-27027 September 1999 Submits Info Re Estimated Effect of Changes or Errors in ECCS Evaluation Models or in Application of Models,Per 10CFR50.46(a)(3)(ii) ML18017A8861999-09-21021 September 1999 Forwards Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations. ML18017A8821999-09-14014 September 1999 Provides Notification That RO Licensed on Harris Plant No Longer Meets Requirements of 10CFR50.21,effective 990826. Name,Docket Number & License Number for Individual Provided in Encl.Encl Withheld,Per 10CFR2.790(a)(6) ML18017A8651999-09-0808 September 1999 Requests Relief from Section XI,IWA-5242(a) Requirement for HNP Class 2 Bolted Connections in Borated Sys.Compliance with Requirement Would Result in Unusual Difficulty Without Compensating Increase in Level of Quality & Safety ML18017A8581999-09-0303 September 1999 Provides Response to NRC 990805 RAI Re Amend Request to Increase Fuel Storage Capacity ML18017A8551999-09-0101 September 1999 Forwards Marked Up Copy of Approved FSAR Section 17.3 with Applicable Duplicated TS Requirements,As Committed to in 990602 Application for Rev to TS ML18017A8541999-08-20020 August 1999 Submits Closure Info for Rev 1,Suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Identified Discrepancies from Review of NRC Rvid Provided HNP-99-134, Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.211999-08-18018 August 1999 Forwards Rev 11 to Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p)(2) & 10CFR50.4(b)(4). Description of Changes Is Provided as Encl 2 to Ltr.Rev Withheld,Per 10CFR73.21 ML18017A8351999-08-10010 August 1999 Corrects Statement Made in 980923 Ltr,By Clarifying That Operation of Inner & Outer Pal Doors Can Be Operated by Control Panels Located Inside & Outside Containment ML18016B0531999-08-0606 August 1999 Forwards Exercise Scenario with Controller Info & Simulation Data for Harris Nuclear Plant Emergency Preparedness Exercise Scheduled for 990921.Without Encl ML18016B0461999-08-0404 August 1999 Forwards LER 99-006-01 Describing Condition Which Resulted in Exceeding TS Requirements for CIVs & TS 4.0.4 for Generic Requirements for Surveillance Testing.Rev Includes Results of Investigation Into Failure to Recognize TS Requirements ML18016B0421999-07-30030 July 1999 Informs That in Ltr Dtd 950330 CP&L Committed to Complete Assessment of Severe Accident Mgt Capabilities & Make Any Identified Enhancements by 981231.Actions Were Completed in July 1998 ML18016B0391999-07-30030 July 1999 Forwards Rev 35 to PLP-201, Emergency Plan. Rev Replaces All Pages of Previous Rev with Exception of EAL Flow Path, Side 1 & 2 & Annex H,Operations Map & Aperature Card. Changes Made by Rev,Listed ML18016B0221999-07-26026 July 1999 Informs That CP&L Proposes to Provide Response to NRC 990414 RAI Re GL 95-07, Pressure-Locking & Thermal-Binding of SR Power-Operated Gate Valves, by 990930 ML18016B0171999-07-16016 July 1999 Forwards Corrected Pages to Annual Radioactive Effluent Release Rept, for 1998 for HNP ML18016B0051999-07-0101 July 1999 Informs of Scheduled Emergency Preparedness Exercise for Shnpp on 990921,per Requirements of 10CFR50,App E.List of 26 Objectives Selected for Evaluation During Exercise,Encl. Without Encl ML18016A9871999-06-14014 June 1999 Forwards Response to NRC 990429 RAI Re License Amend Request to Place Spent Fuel Pools C & D in Service,Dtd 981223.Info Does Not Change Initial Determination That Proposed License Amend Represents No Significant Hazards Consideration ML18016A9831999-06-10010 June 1999 Submits Notification That Reactor Operator Licensed at HNP Has Terminated Employment with Cp&L.Reactor Operator Info Encl.Effective 990528,individuals License Is No Longer Required & CP&L Requests That License Be Terminated ML20212H7521999-06-0404 June 1999 Encourages NRC to Schedule Open Public Forum Which Would Allow Local Citizens to Express Concerns Re Proposed Expansion of high-level Radwaste Storage Capacity at Shearon Harris Npp.With Certificate of Svc.Served on 990624 ML18016A9721999-05-28028 May 1999 Responds to 990309 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs. ML18016B0011999-05-26026 May 1999 Forwards Ltr Received from Hj Jaffe Expressing Concern Re Cpl Proposal to NRC on Dec of 1998 to Make Harris Nuclear Plant Largest Storage Area for High Level Nuclear Waste in Nation ML18016A9631999-05-25025 May 1999 Forwards Periodic Update to FSAR for Hnp.Amend 49 Is Current Through 981128 (End of RFO 8).Some Changes & Analysis Completed After 981128 Have Also Been Included in Amend ML18016A9511999-05-13013 May 1999 Submits Info Re Estimated Effect of Change to ECCS Evaluation Model,As Required by 10CFR50.46 ML18016A9481999-05-0606 May 1999 Forwards NRC Form 396, Certification of Medical Examination by Facility Licensee, for Senior Reactor Operator Licensed to Operate Hnp.Individuals Info Is Proprietary & Is Being Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML20206R2611999-05-0505 May 1999 Requests That NRC Grant Standing to Intervention Sought by Orange County Board of Commissioners Re Proposal by CP&L to Expand Storage of Hlrw at Shnpp.With Certificate of Svc. Served on 990519 ML18016A9451999-05-0404 May 1999 Provides Proprietary Notification That One SRO Has Been Reassigned from Position for Which Util Certified Need for SRO License & Another SRO Has Terminated Employment with Util.Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9441999-05-0404 May 1999 Notifies NRC of Util Completion of Actions Re GL 96-01, Testing of Safety-Related Logic Circuits at Plant ML18016A9351999-04-30030 April 1999 Forwards Info Requested in 990324 RAI as Suppl to 981223 Application for Amend to License NPF-63 for Alternative Plan for Spent Fuel Pool Cooling & Cleanup Sys Piping ML18016A9311999-04-30030 April 1999 Forwards Annual Radioactive Effluent Release Rept for Jan- Dec 1998 & Rev 11 to ODCM for Shnpp HNP-99-068, Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld1999-04-28028 April 1999 Forwards Rev 0 to Physical Security & Safeguards Contingency Plan. Description of Changes Provided.Encl Withheld ML18016A9221999-04-27027 April 1999 Forwards Proprietary Notification That SRO Licensed on Shnpp Has Terminated Employment with Cp&L,Per 10CFR50.74(b). Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML18016A9211999-04-27027 April 1999 Provides Rev 2 to ISI Relief Request 2RG-008, ISI of Class 1,2 & 3 Snubbers (Code Category F-A) Per Plant TS in Lieu of ASME Code Section XI, in Response to 990408 Telcon with NRC ML18016A9161999-04-22022 April 1999 Forwards Proprietary NRC Form 396, Certification of Medical Exam by Facility Licensee, for SRO Licensed to Operate Hnp. License for Individual Should Be Amended IAW Change Noted on Form.Proprietary Encl Withheld,Per 10CFR2.790(a)(6) ML18016A9201999-04-20020 April 1999 Informs of HNP Personnel Changes to Facilitate Proper Distribution of Correspondence.Records Should Be Updated to Reflect Noted Change ML18016A9121999-04-12012 April 1999 Forwards Diskette Containing Data Re Annual Exposure Rept for Individual Monitoring for Personnel Shnpp,Per 10CFR20.2206(b).Without Encl ML18016A9021999-04-12012 April 1999 Forwards Rev 34 to PLP-201, Shearon Harris NPP Emergency Plan, Replacing All Pages of Previous Rev with Exception of EAL Flow Path,Side 1 & 2 & Annex H Operations Map & Aperture Card.Changes,Listed.Rev Summary,Encl ML18016A8911999-04-0505 April 1999 Forwards non-proprietary App 4A,pages 20-25 & Proprietary Page 4-6 to re-issued Rev 3 of Holtec International Licensing Rept HI-971760.Pages Were Inadvertently Omitted from Reissued Rept.Proprietary Page 4-6 Withheld ML18016A8891999-04-0101 April 1999 Forwards Rev 99-1 to Plant EALs for NRC Review & Approval, Per 10CFR50,App E.Encl Provides Comparison of Currently Approved EALs & Proposed Rev 99-01.Approval of EALs Prior to June 1999,requested.With Four Oversize Drawings ML18016A8811999-03-31031 March 1999 Responds to NRC 990301 Ltr Re Violations Noted in Insp Rept 50-400/98-11.Corrective Actions:Post Trip/Safeguards Actuation Rept for 981023,RT Was Corrected,Required Reviews Completed & Approval Obtained on 990219 ML18016A8671999-03-19019 March 1999 Submits Response to RAI Re Spent Fuel Pool Water Level & Revised Fuel Handling Accident Analyses,Per 990317 Telcon with NRC ML18016A8631999-03-19019 March 1999 Forwards Shnpp Operator Training Simulator,Simulator Certification Quadrennial Rept, IAW 10CFR55.45(b)(5)(ii). NRC Form 474 & Required Info Re Simulator Performance Test Results & Schedules Also Encl ML18016A8691999-03-18018 March 1999 Forwards Resolution Adopted by Lee County,North Carolina Board of Commissioners Re Proposed Expansion of high-level Radioactive Waste Storage Facilities at Carolina Power & Light Shearon Harris Nuclear Power Plant ML18016A8511999-03-15015 March 1999 Forwards Proprietary & non-proprietary Version of Rev 3 to HI-971760, Licensing Rept for Expanding Storage Capacity in Harris SFPs 'C' & 'D'. Repts Are Reissued to Reflect Reduction in Proprietary Info.Proprietary Info Withheld ML18016A8601999-03-15015 March 1999 Informs NRC of Mod to Commitment for Hnp,Re Comprehensive Review of Implementation of TS Sr.Upon Completion of Listed Reviews,Surveillance Procedure Review Project Will Be Considered Complete 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0911990-09-12012 September 1990 Confirms That Fee Electronically Transferred to Dept of Treasury for Payment of NRC Review Fees ML18009A6581990-09-11011 September 1990 Submits Addl Info Re Use of Hafnium Control Rods at Facility.All Rods Will Be Removed During Spring 1991 Outage ML20059H4181990-09-0606 September 1990 Responds to NRC Re Violations Noted in Insp Rept 50-400/90-13.Corrective Action:Changes to EST-717 in Area of Power Normalization Under Study for Past Several Months ML17348B4941990-08-30030 August 1990 Forwards Semiannual 10CFR26 fitness-for-duty Program Data for 900103-0630.Mgt Decision Made to Utilize Alcohol Breath Instruments as Screening Devices for Unscheduled Work Call Outs in Determining fitness-for-duty ML20059D3511990-08-30030 August 1990 Forwards Decommissioning Financial Assurance Certification Rept Submitted by North Carolina Eastern Municipal Power Agency ML18009A6261990-08-10010 August 1990 Informs That Action Committed to in Response to Generic Ltr 88-14, Instrument Air Supply Sys, Completed ML18009A6241990-08-0303 August 1990 Forwards Addl Info Re Operator Action Times Assumed in Steam Generator Tube Rupture Analyses for Plant,Per 900712 Telcon ML18009A6081990-07-31031 July 1990 Forwards Plan for Shearon Harris Nuclear Power Plant Emergency Exercise - 900919, Per NRC Request.W/O Encl ML20055J4171990-07-30030 July 1990 Forwards Rev 5 to Security Plan.Rev Withheld (Ref 10CFR73.21) ML20055F9431990-07-12012 July 1990 Advises That Stated Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900711 for Payment of Operator License Exam Fees for Listed Insp Invoices ML18009A5991990-07-0606 July 1990 Comments on Electrical Distribution Sys Functional Insp Rept 50-400/90-200 on 900212-0316.Seismic Qualification Package Subsequently Upgraded to Include Qualification Info Based on Receipt of Part 21 from Transamerica Delaval ML18009A5851990-06-28028 June 1990 Advises That Emergency Preparedness Exercise Scheduled on 900919.Exercise Will Consist of Simulated Accident at Plant Site & Will Involve Planned Response Actions.Objectives to Be Fulfilled Encl ML18009A5621990-05-30030 May 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Rept 50-400/90-06.Corrective Actions:Procedures OST-1008 & OST-1108 Revised to Delete Stroke Testing of Valve 1ST-359 on Quarterly Basis ML18009A5141990-05-0303 May 1990 Forwards Eddy Current Exam CP&L Shearon Harris Nuclear Power Plant Steam Generators A,B & C, Providing Results of Inservice Insps Performed During Plant Second Refueling Outage in Oct 1989 ML18009A4941990-04-26026 April 1990 Forwards Radiological Environ Operating Rept,1989, Radiological Environ Operating Rept,Vol II,Jan-June 1989, Sample Analyses Data & Radiological Environ Operating Rept,Vol III,Jul-Dec 1989,Sample Analyses Data. ML18009A5031990-04-25025 April 1990 Submits Suppl 2 to Relief Request R2-001 Re Plant 10-yr Inservice Insp Plan,Per 880129 Request ML18009A4911990-04-24024 April 1990 Forwards Addl Info Re Proposed Wakesouth Regional Airport to Be Located Near Facility,Per 900411 Request.Info Previously Provided to NRC During 900320 & 23 Telcons ML18009A4841990-04-24024 April 1990 Forwards Corrected Bases marked-up Page to 900226 Tech Spec Change Request Re Surveillance Intervals ML18009A4251990-03-30030 March 1990 Submits Supplemental Response to Station Blackout Rule Based on Guidelines Provided in NUMARC 87-00, Guidelines & Technical Bases for NUMARC Initiatives.... No Changes to Previous Calculations Necessary & One Deviation Noted ML18009A4231990-03-29029 March 1990 Suppls Response to NRC 900216 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Actions:Surveys Performed to Determined Extent & Level of Contamination & Personnel Involved Decontaminated ML18009A4111990-03-23023 March 1990 Responds to NRC 900227 Ltr Re Violations Noted in Insp Rept 50-400/90-02.Corrective Actions:Personnel Involved W/ Quadrant Power Tilt Ratio Calculations & Operability Determination Counseled ML18009A4121990-03-23023 March 1990 Forwards Rev 17 to PLP-201, Emergency Plan & Fission Product Barrier Analysis.Rev to Emergency Plan Incorporates Comments Received During Recent Licensed Operator Requalification Training in Emergency Plan Procedures ML18009A4151990-03-22022 March 1990 Responds to NRC SALP Rept for Jul 1988 - Nov 1989.Contrary to Statement in Rept Significant Amount of Refresher Training Was Conducted During SALP Assessment Period Including Termination & Splicing & Motor & Bus Relays ML18009A4081990-03-19019 March 1990 Responds to NRC 900226 Ltr Re Violations Noted in Insp Rept 50-400/90-01.Corrective Actions:All Calibr Required by Tech Specs for Power Range Nuclear Instrumentation Satisfactorily Completed ML18022A7891990-03-0909 March 1990 Forwards Vols 1 & 2 of Inservice Insp Summary 1st Interval 1st Period,2nd Refueling Outage Completed 891222. ML18022A7881990-03-0606 March 1990 Confirms Understanding of Status of NRC Activities Re Proposed Wakesouth Regional Airport Located Near Plant Site. Pending Issues Should Be Resolved by 900331 to Enable Util to Complete Negotiations W/Airport Authority ML18022A7851990-03-0202 March 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-400/89-34.Corrective Actions:Valve SI-332 Closed & Gravity Drain Path Isolated & Shift Foreman Required to Review MMM-012 Re Priority/Emergency Maint Work Control ML18022A7721990-02-26026 February 1990 Forwards Application for Amend to License NPF-63,revising Tech Spec Surveillance 4.0.2 to Permit Surveillances to Be Extended Up to 25% of Specified Interval & Removing 3.25 Limitation from Spec,Per Generic Ltr 89-14 ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML18022A7701990-02-14014 February 1990 Notifies of Issuance of Renewal of NPDES Permit for Plant. Permit Encl ML18009A3831990-02-0909 February 1990 Responds to 900112 Ltr Re Violation Noted in Insp Rept 50-400/89-35.Corrective Actions:Valves ICS-775 & ICS-776 Added to Inservice Insp Program for Back Seat & Full Flow Testing & ICS-525 Revised to Satisfy Tech Spec Requirements ML18009A3751990-02-0101 February 1990 Forwards Retyped Tech Spec Pages Re 890630 Application for Amend to License NPF-63 Concerning RCS Pressure Temp Limits ML18009A3701990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 IR 05000400/19890281990-02-0101 February 1990 Informs That Planned Corrective Actions Re Violations Noted in Insp Rept 50-400/89-28 Will Not Be Completed Until 900301 ML18009A3631990-01-26026 January 1990 Responds to NRC Bulletin 88-008, Thermal Stratification in Piping Connected to Rcs. Design Differences That Either Minimize Potential of Occurrence or Enhance Possibility of Detection Should Scenario Be Created at Plant Determined ML18009A3531990-01-25025 January 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence ML18009A3501990-01-22022 January 1990 Forwards Revised Tech Spec Table 3.7-6, Area Temp Monitoring, Per 891218 Tech Spec Amend Request ML18022A7591990-01-17017 January 1990 Submits Results of Aircraft Hazards Study Associated W/ Proposed Wakesouth Regional Airport & Facility ML20005G5731990-01-16016 January 1990 Forwards Response to Insp Rept 50-400/89-32.Encl Withheld (Ref 10CFR73.21) ML18009A3351990-01-0505 January 1990 Forwards Rev 16 to Vol 1,Part 2 of Plant Operating Manual PLP-201, Emergency Plan. Revised NUREG-0654 Comparison W/ Plant Emergency Action Level Flow Path Also Encl for Review ML18009A3171989-12-21021 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-21.Corrective Actions:Incident Reviewed by Both Plant & Nuclear Engineering Dept Personnel to Avoid Future Miscommunication ML18009A3181989-12-15015 December 1989 Forwards Retyped Amend Bar Pages to Tech Spec Table 3.3-3 Re Auxiliary Feedwater Manual Initiation,Per 891026 Application for Amend to License NPF-63 ML18009A3011989-12-15015 December 1989 Forwards Proprietary WCAP-12403 & Nonproprietary WCAP-12404, LOFTTR2 Analysis for Steam Generator Tube Rupture W/Revised Operator Action Times for Shearon Harris Nuclear Power Plant. WCAP-12403 Withheld (Ref 10CFR2.790(b)(4)) ML18022A7371989-12-13013 December 1989 Forwards Change 3 to Rev 2 to State of Nc Emergency Response Plan in Support of Shearon Harris Nuclear Power Plant, Incorporating Administrative Enhancements. W/One Oversize Encl ML18009A2971989-12-0808 December 1989 Responds to NRC 891108 Ltr Re Violations Noted in Insp Rept 50-400/89-23.Corrective Action:Min of Four Decontamination Personnel Will Be Assigned 24 H Per Day During Fuel/Cask Handling to Maintain Cleanliness in Fuel Handling Bldg ML18009A2841989-11-30030 November 1989 Forwards Rev 0 to Core Operating Limits Rept in Support of Cycle 3 Operations ML18005B1531989-11-27027 November 1989 Forwards Retyped Amend Bar Pages to 890630 Request for Rev to License NPF-63 Re RCS pressure-temp Limits ML18022A7311989-11-27027 November 1989 Forwards Response to Generic Ltr 89-21, Request for Info Re Status of Implementation of USI Requirements. ML18005B1511989-11-17017 November 1989 Forwards 15-day Special Rept Identifying Number of Steam Generator Tubes Plugged During Current Inservice Insp Period ML18005B1501989-11-13013 November 1989 Suppls 890403 Response to NRC Bulletin 88-010, Nonconforming Molded-Case Circuit Breakers. Addl Nontraceable Molded Case Circuit Breakers (MCCB) & MCCBs Traceable to Refurbishers Noted During Records Review 1990-09-06
[Table view] |
Text
REGULRY INFORMATION DISTRISUTI "SYSTEN (RIDE)
ACCESSION NBR0 8505130355 DOC ~ DATE'f 85/05/07 NOTARIZED ~ NO DOCKET'.
FACILi50 400 Shearon Harr-fs Nuclear Powei" Plantr Unit ir Carolina 05000400 AUTH, NAME AUTHOR AFFILIATION ZIMMERMANES ~ R ~ Car ol {na Power L Light Co ~
RECIP ~ NAME< RECIPIENT AFFILIATION DENTONEH,R ~, Off fce of Nuclear 'Reactor>> R'egulatfonr Dir actor>>
SUBJECT:
Forwards addi {nfo re* fire protectfonrsueplement)ng 850019 submftta)r fn,resPonse to verbal r;equest'or clarificatfon from. Aux[1 fary Sys Branch revfe4ei Info covers>> alternate" shutdown sys, DISTRISUTION CODES SOOED COPIES'ECEIVED:LTR Q'NCL TITLE". Ld censing Submi t tal: Ff r e>>'Protection j SIZE:
NOTES!
RECIPIENT COPIES" RECIPIENT'D COPIES ID CODE/NAME>>>> LTTR ENCL CODE/NAME>> LTVR ENCL NRR>> L83>> BC 1<<1 BUCKLEYEB 01 1 1 INTERNAL!- ACRS 10 6 6 ADM/LFMB 1 0 ELD/HDS1 1- 0 NRR/ . EB 06 p NRR/DS I/AS8 1 1 0$ 1 RGNEs 1 ~
1 EXTERNALS LPDR 03>> 1 1 NRC PDR NSIC 05>> 1 1 02'TOTAL NUMBER: OF COPIES'EQUIREDt LTTR 18 ENCL 16
l gL r I <<<<1
~ )
P 1 Isv I L q frit t I 1<<1 hatt<<
a t l)1 a'll 1 '<<S '11 r <<<<$ SV K r t IJl I v <<
S
~ C it r1 ',,rl II
'I 1, V X II!
<<4 V <<0 ltt,& jl 1g ~r> t IW <<r ll.tj f ",11 ~t 1rjfrtl g s'I <<11<< wt << ii) f 1 tSII - ' 1<<tI I <<\ f v 1rli t '1( <1
~ I.,'K, I"
<<& ~ << ]f gjl, I
, [sv II
'I It s1 ,'~,1
~ v 7 , VK
>i ll A Ij ",
I'"
ft I
j 1 K
<<1
'l f, ~ <<c Q f,
@ME Carolina Power 8 Light Company SERIAL: NLS-85-158 qg Ov >Sa5 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 - DOCKET NO.50-000 FIRE PROTECTION
Dear Mr. Denton:
Carolina Power R Light Company (CPRL) hereby submits additional information concerning fire protection at Shearon Harris Nuclear Power Plant. The enclosed information is submitted in response to a verbal request for clarification from the Auxiliary System Branch reviewer and supplements CPRL's April 19, 1985 submittal (NLS-85-132).
If you have any questions concerning this material or require additional information, please contact me.
Yours very truly, S. R Zi erman nager Nuclear Licensing Section DCM/crs (1003DCM)
Enclosure cc: Mr. B. C. Buckley (NRC) Mr. Wells Eddleman Mr. G. F. Maxwell (NRC-SHNPP) Mr. John D. Runkle Dr. J. Nelson Grace (NRC-RII) Dr. Richard D. Wilson Mr. Travis Payne (KUDZU) Mr. G. O. Bright (ASLB)
Mr. Daniel F. Read (CHANGE/ELP) Dr. J. H. Carpenter (ASLB)
Wake County Public Library Mr. J. L. Kelley (ASLB) 8505130355 850507 PDR ADOCX 05000400 F PDR o>>
411 Fayettevilte Street o P. O. 8ox 1551 o Raleigh, N. C. 27602
4 REACTOR SHUTDOWN BY USE OF THE ALTERNATIVESHUTDOWN SYSTEM In general, recognizing the confined physical location of fires and the operational flexibilityand physical diversity of systems available to achieve safe shutdown, one can assume that the plant's defense in depth fire protection features will limit fire damage to the extent that unaffected plant systems will be able to attain safe shutdown. An extensive effort would be required to identify the effects of postulated fires in potential plant locations on the plant systems which are normally available to support safe shutdown. As a conservative alternative to this approach, a minimum set of plant systems (safe shutdown systems) and components is identified in response to the requirements of 10 CFR 50 Appendix R. The identified systems and components can achieve and maintain safe shutdown regardless of the location of the fire and the loss of offsite power. Demonstration of adequate protection of this minimum set of systems from the effects of postulated fires constitutes an adequate and conservative demonstration of the ability to achieve and maintain safe shutdown for the purposes of fire protection.
The safe shutdown systems selected for SHNPP are capable of achieving and maintaining subcritical conditions in the reactor, maintaining reactor coolant inventory, maintaining reactor coolant pressure control, removing decay heat, achieving cold shutdown condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and maintaining cold shutdown conditions thereafter.
The following is a list and description of the specific shutdown functions necessary to satisfy the Alternative Shutdown System acceptance criteria:
- 1) Reactor Reactivity Control
- 2) Reactor Coolant System Inventory Control
- 3) Reactor Coolant Pressure Control
- 0) Reactor Heat Removal
- 5) Process Monitoring
- 6) Miscellaneous Supporting Functions As stated in our April 5, 1985 submittal in response to 010.05, the SHNPP design utilizes Alternative Shutdown following a fire induced evacuation of the Control Room. The SHNPP safe shutdown analysis assumes the reactor is tripped prior to control room evacuation. This is consistant with the staff guidance provided in Generic Letter 85-01.
The remaining operator actions required to take control of plant systems from the alternative shutdown system are carried out from fire zones unassociated with the control room.
Ma'or E ui ment Available from Alternative Shutdown
- 1) Reactor Reactivity Control Reactor reactivity control is initially achieved by tripping the control rods into the core prior to control room evacuation. The reactor reactivity control function will provide sufficient shutdown margin to ensure that (1) the reactor can be made subcritical from required operating conditions, and (2) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
(1443DCM/crs)
The two means of reactivity control are: (I) control rods, which provide the immediate shut'down reactivity (initiated prior to control room evacuation), and (2) soluble boron addition to the RCS from the boric acid tank by the boric acid transfer pump (SB) and the charging/safety injection pump (SB). This will maintain adequate shutdown margin for the transition from Hot Standby to Cold Shutdown.
No postulated fire will prevent the addition of soluble boron necessary to maintain required shutdown margin throughout the shutdown period. Available indication was provided in CPRL's April 5, 1985 response to 010.06.
Reactor Coolant System Inventory Control The reactor coolant system inventory control function will ensure sufficient makeup inventory is provided for:
o Reactor coolant system fluid losses due to reactor coolant system leakage, and o Shrinkage of the reactor coolant system water volume during cooldown from Hot Standby to Cold Shutdown conditions.
Adequate performance of this function is assured by maintaining reactor coolant level within the pressurizer.
Inventory makeup to the RCS will be from the boric acid tank by a charging path as described in I above. A back-up supply of borated water is available from the Refueling Water Storage Tank. The negative reactivity inserted by the control rods and boron addition will maintain the reactor core-subcritical with adequate Shutdown Margin while cooling down the RCS.
Reactor Coolant Pressure Control Reactor coolant pressure control ensures that (l) reactor coolant system integrity is maintained by providing overpressure protection, and (2) sufficient subcooling margin is provided to minimize void formation within the reactor vessel. RCS pressure can be maintained by energization of the pressurizer heaters (SB power supply). Overpressure protection of the RCS is provided for in Hot Standby (prior to cooldown and depressurization) by the pressurizer safety valves. Depressurization capability is provided by the pressurizer power-operated relief valves (PORVs) (SB power supply). After depressurization, when the RCS is aligned with the Residual Heat Removal System (RHR), overpressure protection is provided by RHR suction relief valves.
Adequate subcooled margin is achieved and maintained by operator action using pressure and temperature information received from the RCS pressure and temperature instrumentation. (Indication was provided in April 5 response to Olo.O6.)
Reactor Heat Removal The reactor heat removal function is capable of transferring fission product decay heat from the reactor core at a rate such that specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. Following a reactor trip with an assumed loss of offsite power, decay (14430'/crs )
,heat is initially removed by natural circulation of the RCS, heat transfer to the main steam system through the steam generators, and operation of main steam PORVs (S/G AkC). Decay heat removal requires that sufficient feedwater be supplied to the steam generators to make up for the inventory discharged as steam by the main steam power-operated relief valves. The turbine driven auxiliary feedwater pump will supply sufficient feedwater to make up for'nventory losses during initial maintenance of Hot Standby and subsequent cooldown. Feedwater is available from the condensate storage tank, and alternatively from the emergency service water system.
Hot standby can be maintained for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> followed by 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of cooldown to hot shutdown condition. Hot standby can be maintained beyond this 16-hour period by use of the Emergency Service Water System a back-up source of Auxiliary Feedwater water to the Condensate Storage Tank.
After reduction of reactor coolant system temperature below 350'F, the RHR system (SB) is used (via valves 1RH-V 500 SB and 501 SA) to establish long-germ
'ore cooling through the removal of decay heat from the RCS through the
, component cooling water system (SB) and the emergency service water system (SB). Assuming only 1 RHR heat exchanger I RHR pump are in service, cold shutdown can be achieved within 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />.
- 5) Process Monitoring The process monitoring function is capable of providing readings of those plant process variables necessary for plant operators to perform and/or control the above identified functions. The available indicators were provided in CPRL's April 5, 1985 response to 010.06.
- 6) Miscellaneous Support Functions The systems and equipment used to perform the functions described above in items 1-0 may require miscellaneous supporting functions. The major supporting functions are ac/dc power (D/G SB), Essential Services Chilled Water (SB), and HVAC to essential components (SB). These supporting functions will be available and capable of providing the support necessary to ensure acceptable performance of the previously identified safe shutdown features.
(14430CH/crs )
~ ~
4