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| {{#Wiki_filter:REQULAT INFORl'tATION DIBTRIBUTIO STEl'1<RIDS)'CCESBIQN NBR: 8605270104 DQC.DATE: 86/05/f 9 NOTAR'I ZED: NO DOCKET FACIL: 50-400 Sheav on Hav v is Nucleav Poeev'lant> | | {{#Wiki_filter:REQULAT INFORl'tATION DIBTRIBUTIO STEl'1 <RIDS) |
| Unit 1>Cav.ol ina 05000400 AUTH.MANE AUTHOR AFFILIATION ZINNERNAN> | | 'CCESBIQN NBR: 8605270104 DQC. DATE: 86/05/ f 9 NOTAR'I ZED: NO DOCKET FACIL: 50-400 Sheav on Hav v is Nucleav Poeev'lant> Unit 1> Cav.ol ina 05000400 AUTH. MANE AUTHOR AFFILIATION ZINNERNAN> B. R. Cav olivia Polllev'c Light CD. |
| B.R.Cav olivia Polllev'c Light CD.RECIP.Nhl'1E REC IP I ENT AFF1 LIAT ION DENTON>H.R.Office of Nucleav Reactov Regulation> | | RECIP. Nhl'1E REC IP I ENT AFF1 LIAT ION DENTON> H. R. Office of Nucleav Reactov Regulation> Div ectov'post 851125 |
| Div ectov'post 851125 | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Fov'b'av'ds addi info v.e post-accident sampling sos>including Rev 0 to Chemistv g 8r Radiochemistv g Pv oceduv e CRC-826>"Post-Accident Sample Chlovide Apalgsis>" per SER License Condition 3 5 NUREC-0737> | | Fov'b'av'ds addi info v.e post-accident sampling sos> including Rev 0 to Chemistv g 8r Radiochemistv g Pv oceduv e CRC-826> |
| Item II.B.3.DISTRIBUTION CODE: B001D COPIES RECEIVED: LTR ENCL SIZE: TITLE: Licensing Submittal: | | "Post-Accident Sample Chlovide Apalgsis>" per SER License Condition 3 5 NUREC-0737> Item II. B. 3. |
| PSAR/FSAR Amdts Zt Related Cov'v espondence NOTES: Application fov pev mit v enewal filed.05000400 REC I P IENT ID CODE/NAl'IE pNR-A ADTB PWR-A EICSB pWR-A PD2 LA BUCKLEY, B 01 pNR-A RBB INTERNAL: ADN/LFNB IE FILE IE/DGAVT/GAB 21 NRR PNR-A ADTS NRR ROE.N.L NRR/DHFT/NTB RCN2 EXTERNAL: 24X DNB/DBS (AIIDTS)NRC PDR 02 pNL GRUEL.R COPIES LTTR ENCL 1 1 2 2 1 2 2 1 1 0 1 1 1 1 0 1 1 3 3 1 1 RECIPIENT ID CODE/NANE PWR-A EB PNR-A FOB PWR-A PD2 PD PWR-A PSB ELD/HDS1 IE/DEPER/EPB 36 NRR BNR ADTB NRR PWR-B ADTS NRR/DHFT/HFIB ILE 04/NI B BNL<ANDTB ONLY)LPDR 03 NBIC 05 COPIES LTTR ENCL 1 1 1 1 1 0 1 0 0 1 0 f 1 TOTAL NUNBER QF, COPIES REQUIRED: LTTR 34 ENCL 28 N~t>>'~,f>>N 4 EN I I>>C'~-*" 1 4 h(e I 1$4 f 4 ht,>>'',t4 NN (4~i")1.d Nf, 4 NI SE 4144>>4 Cf S.0 I I 4 I>>'(~tt$"$f'(3>ff j yf''d'dff''ft.'4 N If f(r,l d 1 1 4 ff,>>4 SN~">>f~I 44'j'!d 4(If I*4,'I 4 4 4 h" St(jj, 44 f",I'h N>>N I 4'4 II'N', I>>(I Elf(II h 4 hl d!41~4 IEI!It 4 II'-!IS 4)SI I",4>>h CNK Carolina Power&Light Company MAY 1S 1986 SERIAL: NLS-86-108 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.I-DOCKET NO.50-000 POST ACCIDENT SAMPLING SYSTEM | | DISTRIBUTION CODE: B001D COPIES RECEIVED: LTR ENCL SIZE: |
| | TITLE: Licensing Submittal: PSAR/FSAR Amdts Zt Related Cov'v espondence NOTES: Application fov pev mit v enewal filed. 05000400 I |
| | REC P IENT COPIES RECIPIENT COPIES ID CODE/NAl'IE LTTR ENCL ID CODE/NANE LTTR ENCL pNR-A ADTB 1 1 PWR-A EB 1 1 PWR-A EICSB 2 2 PNR-A FOB pWR-A PD2 LA 1 PWR-A PD2 PD 1 BUCKLEY, B 01 2 2 PWR-A PSB 1 pNR-A RBB 1 1 INTERNAL: ADN/LFNB 0 ELD/HDS1 1 0 IE FILE 1 1 IE/DEPER/EPB 36 1 IE/DGAVT/GAB 21 1 NRR BNR ADTB 0 NRR PNR-A ADTS 1 0 NRR PWR-B ADTS 0 NRR ROE. N. L 1 NRR/DHFT/HFIB NRR/DHFT/NTB 1 ILE 04 1 RCN2 3 3 /NIB 0 EXTERNAL: 24X 1 BNL<ANDTB ONLY) f DNB/DBS (AIIDTS) LPDR 03 NRC PDR 02 1 NBIC 05 1 pNL GRUEL. R TOTAL NUNBER QF, COPIES REQUIRED: LTTR 34 ENCL 28 |
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| ==Dear Mr.Denton:== | | N ~ |
| Carolina Power R Light Company hereby submits additional information concerning the Post Accident Sampling System (PASS)at the Shearon Harris Nuclear Power Plant.This information is being submitted in response to Safety Evaluation Report License Condition No.3 and NUREG-0737 Item II.B.3.The attached information responds to specific questions from your staff concerning the demonstration of the applicability of PASS procedures and instrumentation in the post-accident water chemistry and radiation environment, and retraining of operators on a semiannual basis.In addition, attached is information concerning the accuracy, range, and sensitivity of each of the radionuclide and chemical analyses with copies of the appropriate plant procedures. | | t>> |
| If you have any additional questions or require further information, please contact me.Yours very truly, SRZ/JDK/pgp (3789JDK)Attachments gg4frs44~- | | '~ |
| S.R, Zi merman I nager Nuclear Licensing Section cc: Mr.B.C.Buckley (NRC)Dr.J.Nelson Grace (NRC-RII)Mr.G.F.Maxwell (NRC-SHNPP) | | I 1 |
| ~Mr.Jim Wing(NRC)Mr.Travis Payne (KUDZU)Mr.Daniel F.Read (CHANGE/ELP) | | , f>>N 4 EN I C'~ |
| Wake County Public Library'r.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)B~og27og04 860 pDR ADOCH 0 Fro'g E 411 Fayettevilte Street o P.O.Box 1551~Raleigh, N.C.27602 C~g/~r<I'I NRC QUESTION 1: Demonstrate applicability of procedures and instrumentation in the post accident water chemistry and radiation environment, and retraining of operators on semiannual basis.CPRL RESPONSE: The boron and chloride analyses methods were tested using the standard test matrix suggested in the NUREG-0737 (II.B.3)clarification guidelines.
| | >> |
| Although the actual matrix solution used in the plant did not include exposure to gamma radiation, similar methods had been successfully tested by our consultant (NUS Corporation) with exposure to varying amounts of gamma radiation. | | *" 1 4 h(e I $4 f 4 |
| The boron analysis is performed using a 1:1000 dilution.A 5 mL aliquot of diluted sample is used.The estimated radiation dose to the fluoroborate selective ion electrode is in the range of tens to hundreds of rads based on a diluted sample radiation level of 30 R/hr at 1 cm two hours after the accident and an exposure time of 15 minutes.Based on experience with otitpr electrometric probes, such as pH probes, which are stable at cumulative doses up to 10-10 rads, no significant effect on the accuracy of the boron determination or the operating life time of the probe is anticipated. | | ht,>>'',t4 (4 ~i " ) 1 . |
| This evaluation was confirmed by Exxon Nuclear Idaho Company and documented in"Evaluation of GE and SEC Chemical Procedures for Post-Accident Analysis of Reactor Coolant Samples," Exxon Nuclear Idaho Company, November 1981.Post-accident chloride analysis at SHNPP will be performed by ion chromatography using a 100 p L aliquot of a 1:100 diluted sample.Thus, the total radiation dose from one analysis would be in the range of tens to hundreds of rads based on a sample radiation level of 30 R/hr for a 20 minute analysis.Components in the ion chromatograph receiving this radiation exposure include the following: | | d Nf, SE 4 |
| Cation resin Anion resin Conductivity cell Transistors Capacitors Wire-wound pots Circuit board No radiation damage is anticipated with resins based on experience throughout the nuclear industry.Resins used in purification system ion exchangers in nuclear plants experience radiation doses orders of magnitude higher than the dose anticipated for the ion chromatograph under accident conditions. | | 4144>>4 |
| Resins are conventionally used to separate various radionuclides under high radiation conditions at Battelle without problems.Damage occurs after extended exposure;however, the degradation process isglow.Anion resin will start to degrade at about 10 rads and cation resins at 5 x 10 rads.It is anticipated that electronic components of the type inQuded in the ion chromatot',raph will be resistant to cumulative exposure well above 10 rads.(3789JDK/pgp) t f Based on the above, the boron methods using fluoroborate ion specific electrode and chloride method using ion chromatograph meet the matrix testing requirements. | | '( |
| CPdcL will retrain the chemistry technicians semiannually. | | NI Cf S .0 NN I I 4 |
| This retraining will consist of retraining approximately half of the technicians quarterly in conjunction with the quarterly operability verification testing of the PASS.(3789JDK/pgp) | | I>> ~ tt$ |
| NRC QUESTION 2: Provide the accuracy, range, and sensitivity for post-accident boron and chloride analyses.Also provide the plant procedures for chemical analyses.CPRL RESPONSE: NUS Operating Services Corporation (NUSOSC), consultant, performed matrix testing at SHNPP for boron and chloride analysis.The results indicate that SHNPP procedures for boron (CRC-827)and chloride (CRC-826)meet the NUREG-0737 (II.B.3)requirements regarding accuracy, range, and sensitivity. | | " |
| The matrix test results are: Boron+396 at 2.0 ppm+1096 at 0.5 ppm Parameter A~ccurac~Ran e 500-6000 ppm Dilution 1 to 1000 Chloride+1.296 at 100 ppb)10.0 ppm 1 to 100 Chloride analysis of a diluted sample will be used for initial scoping.More accurate chloride analysis will be performed on an undiluted sample that has been decayed sufficiently to be in conformance with ALARA within 30 days.Copies of SHNPP Procedures CRC-827 and CRC-826 are attached.(3789 JDK/pgp) t}} | | $ |
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| | CNK Carolina Power & Light Company SERIAL: NLS-86-108 MAY 1S 1986 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. I - DOCKET NO. 50-000 POST ACCIDENT SAMPLING SYSTEM |
| | |
| | ==Dear Mr. Denton:== |
| | |
| | Carolina Power R Light Company hereby submits additional information concerning the Post Accident Sampling System (PASS) at the Shearon Harris Nuclear Power Plant. This information is being submitted in response to Safety Evaluation Report License Condition No. 3 and NUREG-0737 Item II.B.3. The attached information responds to specific questions from your staff concerning the demonstration of the applicability of PASS procedures and instrumentation in the post-accident water chemistry and radiation environment, and retraining of operators on a semiannual basis. In addition, attached is information concerning the accuracy, range, and sensitivity of each of the radionuclide and chemical analyses with copies of the appropriate plant procedures. |
| | If you have any additional questions or require further information, please contact me. |
| | Yours very truly, gg4frs44~ |
| | S. R, IZi merman nager Nuclear Licensing Section |
| | 'r. |
| | SRZ/JDK/pgp (3789JDK) |
| | Attachments cc: Mr. B. C. Buckley (NRC) Wells Eddleman Dr. J. Nelson Grace (NRC-RII) Mr. John D. Runkle Mr. G. F. Maxwell (NRC-SHNPP) Dr. Richard D. Wilson |
| | ~ |
| | Mr. Jim Wing(NRC) Mr. G. O. Bright (ASLB) |
| | Mr. Travis Payne (KUDZU) Dr. J. H. Carpenter (ASLB) |
| | Mr. Daniel F. Read (CHANGE/ELP) Mr. J. L. Kelley (ASLB) |
| | Wake County Public Library B~og27og04 860 pDR ADOCH 0 Fro |
| | 'g E 411 Fayettevilte Street o P. O. Box 1551 ~ Raleigh, N. C. 27602 |
| | |
| | C |
| | ~ g |
| | / |
| | r< |
| | ~ |
| | I |
| | 'I |
| | |
| | NRC QUESTION 1: |
| | Demonstrate applicability of procedures and instrumentation in the post accident water chemistry and radiation environment, and retraining of operators on semiannual basis. |
| | CPRL RESPONSE: |
| | The boron and chloride analyses methods were tested using the standard test matrix suggested in the NUREG-0737 (II.B.3) clarification guidelines. Although the actual matrix solution used in the plant did not include exposure to gamma radiation, similar methods had been successfully tested by our consultant (NUS Corporation) with exposure to varying amounts of gamma radiation. |
| | The boron analysis is performed using a 1:1000 dilution. A 5 mL aliquot of diluted sample is used. The estimated radiation dose to the fluoroborate selective ion electrode is in the range of tens to hundreds of rads based on a diluted sample radiation level of 30 R/hr at 1 cm two hours after the accident and an exposure time of 15 minutes. |
| | Based on experience with otitpr electrometric probes, such as pH probes, which are stable at cumulative doses up to 10 -10 rads, no significant effect on the accuracy of the boron determination or the operating life time of the probe is anticipated. This evaluation was confirmed by Exxon Nuclear Idaho Company and documented in "Evaluation of GE and SEC Chemical Procedures for Post-Accident Analysis of Reactor Coolant Samples," Exxon Nuclear Idaho Company, November 1981. |
| | Post-accident chloride analysis at SHNPP will be performed by ion chromatography using a 100 p L aliquot of a 1:100 diluted sample. Thus, the total radiation dose from one analysis would be in the range of tens to hundreds of rads based on a sample radiation level of 30 R/hr for a 20 minute analysis. Components in the ion chromatograph receiving this radiation exposure include the following: |
| | Cation resin Anion resin Conductivity cell Transistors Capacitors Wire-wound pots Circuit board No radiation damage is anticipated with resins based on experience throughout the nuclear industry. Resins used in purification system ion exchangers in nuclear plants experience radiation doses orders of magnitude higher than the dose anticipated for the ion chromatograph under accident conditions. Resins are conventionally used to separate various radionuclides under high radiation conditions at Battelle without problems. |
| | Damage occurs after extended exposure; however, the degradation process isglow. |
| | Anion resin will start to degrade at about 10 rads and cation resins at 5 x 10 rads. It is anticipated that electronic components of the type inQuded in the ion chromatot',raph will be resistant to cumulative exposure well above 10 rads. |
| | (3789JDK/pgp) |
| | |
| | f t |
| | |
| | Based on the above, the boron methods using fluoroborate ion specific electrode and chloride method using ion chromatograph meet the matrix testing requirements. |
| | CPdcL will retrain the chemistry technicians semiannually. This retraining will consist of retraining approximately half of the technicians quarterly in conjunction with the quarterly operability verification testing of the PASS. |
| | (3789JDK/pgp) |
| | |
| | NRC QUESTION 2: |
| | Provide the accuracy, range, and sensitivity for post-accident boron and chloride analyses. Also provide the plant procedures for chemical analyses. |
| | CPRL RESPONSE: |
| | NUS Operating Services Corporation (NUSOSC), consultant, performed matrix testing at SHNPP for boron and chloride analysis. The results indicate that SHNPP procedures for boron (CRC-827) and chloride (CRC-826) meet the NUREG-0737 (II.B.3) requirements regarding accuracy, range, and sensitivity. |
| | The matrix test results are: |
| | Parameter A~ccurac ~Ran e Dilution Boron + 396 at 2.0 ppm 500-6000 ppm 1 to 1000 |
| | + 1096 at 0.5 ppm Chloride + 1.296 at 100 ppb ) 10.0 ppm 1 to 100 Chloride analysis of a diluted sample will be used for initial scoping. More accurate chloride analysis will be performed on an undiluted sample that has been decayed sufficiently to be in conformance with ALARAwithin 30 days. |
| | Copies of SHNPP Procedures CRC-827 and CRC-826 are attached. |
| | (3789 JDK/pgp ) |
| | |
| | t}} |
|
|---|
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
REQULAT INFORl'tATION DIBTRIBUTIO STEl'1 <RIDS)
'CCESBIQN NBR: 8605270104 DQC. DATE: 86/05/ f 9 NOTAR'I ZED: NO DOCKET FACIL: 50-400 Sheav on Hav v is Nucleav Poeev'lant> Unit 1> Cav.ol ina 05000400 AUTH. MANE AUTHOR AFFILIATION ZINNERNAN> B. R. Cav olivia Polllev'c Light CD.
RECIP. Nhl'1E REC IP I ENT AFF1 LIAT ION DENTON> H. R. Office of Nucleav Reactov Regulation> Div ectov'post 851125
SUBJECT:
Fov'b'av'ds addi info v.e post-accident sampling sos> including Rev 0 to Chemistv g 8r Radiochemistv g Pv oceduv e CRC-826>
"Post-Accident Sample Chlovide Apalgsis>" per SER License Condition 3 5 NUREC-0737> Item II. B. 3.
DISTRIBUTION CODE: B001D COPIES RECEIVED: LTR ENCL SIZE:
TITLE: Licensing Submittal: PSAR/FSAR Amdts Zt Related Cov'v espondence NOTES: Application fov pev mit v enewal filed. 05000400 I
REC P IENT COPIES RECIPIENT COPIES ID CODE/NAl'IE LTTR ENCL ID CODE/NANE LTTR ENCL pNR-A ADTB 1 1 PWR-A EB 1 1 PWR-A EICSB 2 2 PNR-A FOB pWR-A PD2 LA 1 PWR-A PD2 PD 1 BUCKLEY, B 01 2 2 PWR-A PSB 1 pNR-A RBB 1 1 INTERNAL: ADN/LFNB 0 ELD/HDS1 1 0 IE FILE 1 1 IE/DEPER/EPB 36 1 IE/DGAVT/GAB 21 1 NRR BNR ADTB 0 NRR PNR-A ADTS 1 0 NRR PWR-B ADTS 0 NRR ROE. N. L 1 NRR/DHFT/HFIB NRR/DHFT/NTB 1 ILE 04 1 RCN2 3 3 /NIB 0 EXTERNAL: 24X 1 BNL<ANDTB ONLY) f DNB/DBS (AIIDTS) LPDR 03 NRC PDR 02 1 NBIC 05 1 pNL GRUEL. R TOTAL NUNBER QF, COPIES REQUIRED: LTTR 34 ENCL 28
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CNK Carolina Power & Light Company SERIAL: NLS-86-108 MAY 1S 1986 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. I - DOCKET NO.50-000 POST ACCIDENT SAMPLING SYSTEM
Dear Mr. Denton:
Carolina Power R Light Company hereby submits additional information concerning the Post Accident Sampling System (PASS) at the Shearon Harris Nuclear Power Plant. This information is being submitted in response to Safety Evaluation Report License Condition No. 3 and NUREG-0737 Item II.B.3. The attached information responds to specific questions from your staff concerning the demonstration of the applicability of PASS procedures and instrumentation in the post-accident water chemistry and radiation environment, and retraining of operators on a semiannual basis. In addition, attached is information concerning the accuracy, range, and sensitivity of each of the radionuclide and chemical analyses with copies of the appropriate plant procedures.
If you have any additional questions or require further information, please contact me.
Yours very truly, gg4frs44~
S. R, IZi merman nager Nuclear Licensing Section
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SRZ/JDK/pgp (3789JDK)
Attachments cc: Mr. B. C. Buckley (NRC) Wells Eddleman Dr. J. Nelson Grace (NRC-RII) Mr. John D. Runkle Mr. G. F. Maxwell (NRC-SHNPP) Dr. Richard D. Wilson
~
Mr. Jim Wing(NRC) Mr. G. O. Bright (ASLB)
Mr. Travis Payne (KUDZU) Dr. J. H. Carpenter (ASLB)
Mr. Daniel F. Read (CHANGE/ELP) Mr. J. L. Kelley (ASLB)
Wake County Public Library B~og27og04 860 pDR ADOCH 0 Fro
'g E 411 Fayettevilte Street o P. O. Box 1551 ~ Raleigh, N. C. 27602
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NRC QUESTION 1:
Demonstrate applicability of procedures and instrumentation in the post accident water chemistry and radiation environment, and retraining of operators on semiannual basis.
CPRL RESPONSE:
The boron and chloride analyses methods were tested using the standard test matrix suggested in the NUREG-0737 (II.B.3) clarification guidelines. Although the actual matrix solution used in the plant did not include exposure to gamma radiation, similar methods had been successfully tested by our consultant (NUS Corporation) with exposure to varying amounts of gamma radiation.
The boron analysis is performed using a 1:1000 dilution. A 5 mL aliquot of diluted sample is used. The estimated radiation dose to the fluoroborate selective ion electrode is in the range of tens to hundreds of rads based on a diluted sample radiation level of 30 R/hr at 1 cm two hours after the accident and an exposure time of 15 minutes.
Based on experience with otitpr electrometric probes, such as pH probes, which are stable at cumulative doses up to 10 -10 rads, no significant effect on the accuracy of the boron determination or the operating life time of the probe is anticipated. This evaluation was confirmed by Exxon Nuclear Idaho Company and documented in "Evaluation of GE and SEC Chemical Procedures for Post-Accident Analysis of Reactor Coolant Samples," Exxon Nuclear Idaho Company, November 1981.
Post-accident chloride analysis at SHNPP will be performed by ion chromatography using a 100 p L aliquot of a 1:100 diluted sample. Thus, the total radiation dose from one analysis would be in the range of tens to hundreds of rads based on a sample radiation level of 30 R/hr for a 20 minute analysis. Components in the ion chromatograph receiving this radiation exposure include the following:
Cation resin Anion resin Conductivity cell Transistors Capacitors Wire-wound pots Circuit board No radiation damage is anticipated with resins based on experience throughout the nuclear industry. Resins used in purification system ion exchangers in nuclear plants experience radiation doses orders of magnitude higher than the dose anticipated for the ion chromatograph under accident conditions. Resins are conventionally used to separate various radionuclides under high radiation conditions at Battelle without problems.
Damage occurs after extended exposure; however, the degradation process isglow.
Anion resin will start to degrade at about 10 rads and cation resins at 5 x 10 rads. It is anticipated that electronic components of the type inQuded in the ion chromatot',raph will be resistant to cumulative exposure well above 10 rads.
(3789JDK/pgp)
f t
Based on the above, the boron methods using fluoroborate ion specific electrode and chloride method using ion chromatograph meet the matrix testing requirements.
CPdcL will retrain the chemistry technicians semiannually. This retraining will consist of retraining approximately half of the technicians quarterly in conjunction with the quarterly operability verification testing of the PASS.
(3789JDK/pgp)
NRC QUESTION 2:
Provide the accuracy, range, and sensitivity for post-accident boron and chloride analyses. Also provide the plant procedures for chemical analyses.
CPRL RESPONSE:
NUS Operating Services Corporation (NUSOSC), consultant, performed matrix testing at SHNPP for boron and chloride analysis. The results indicate that SHNPP procedures for boron (CRC-827) and chloride (CRC-826) meet the NUREG-0737 (II.B.3) requirements regarding accuracy, range, and sensitivity.
The matrix test results are:
Parameter A~ccurac ~Ran e Dilution Boron + 396 at 2.0 ppm 500-6000 ppm 1 to 1000
+ 1096 at 0.5 ppm Chloride + 1.296 at 100 ppb ) 10.0 ppm 1 to 100 Chloride analysis of a diluted sample will be used for initial scoping. More accurate chloride analysis will be performed on an undiluted sample that has been decayed sufficiently to be in conformance with ALARAwithin 30 days.
Copies of SHNPP Procedures CRC-827 and CRC-826 are attached.
(3789 JDK/pgp )
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