|
|
| (One intermediate revision by the same user not shown) |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:_ . - - ...._.AEC:3U'" ION FOR PART 50 DCCKET m AL*.(TCiPORARY F0EM) | | {{#Wiki_filter:_ . - - . . |
| CONTROL NO: 7085 | | . AEC :3U'" ION FOR PART 50 DCCKET m AL (TCiPORARY F0EM) CONTROL NO: 7085 FILE: - |
| *FILE: -FROM: DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Metropolitan Edison Company Reading Pa. 19603 9-10-73 9-21-73 X J. G. Miller TO: ORIG CC OTHER SENT AEC PDR X A. Giambusso 1 signed SENT LOCAL PDR X CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
| | FROM: DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Metropolitan Edison Company Reading Pa. 19603 9-10-73 9-21-73 X J. G. Miller TO: ORIG CC OTHER SENT AEC PDR X A. Giambusso 1 signed SENT LOCAL PDR X CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO: |
| 7'5'0 2'89 %
| | XX 1 '5'072'89 % |
| XX 1 w --DESCRIPTICN:
| | w -- |
| ENCLOSURES: | | DESCRIPTICN: ENCLOSURES: |
| Ltr re ACRS 8-14-73 ler. . . . . . . . Trans the fol-Post Accident Instrumentation- instrumentation lowing: for determining the course of potentially serious accident ACKNOWLEDGED DO NOT REMOVE PLANT NAME: Three Mile Island Unit-1 ( l cys rec'd ) | | Ltr re ACRS 8-14-73 ler. . . . . . . . Trans the fol- Post Accident Instrumentation- instrumentation lowing: for determining the course of potentially serious accident ACKNOWLEDGED DO NOT REMOVE PLANT NAME: Three Mile Island Unit-1 ( l cys rec'd ) |
| FOR ACTICN/INFORMATION 9-21-73 GC BUTLER (L) dCBJENCER(L) | | FOR ACTICN/INFORMATION 9-21-73 GC BUTLER (L) dCBJENCER(L) ZIEMANN(L) REGAN(E) |
| ZIEMANN(L) | | W/ Copies W/ 2 Copies W/ Copies W/ Copies CLARK (L) STOLZ(L) DICKER (E) |
| REGAN(E)W/ Copies W/ 2 Copies W/ Copies W/ Copies CLARK (L)STOLZ(L)DICKER (E) | | W/ Copies W/ Copies W/ Copies W/ Copies COLLER(L) VASSALLO(L) KNIGH' ION (E) |
| W/ Copies W/ Copies W/ Copies W/ Copies COLLER(L)VASSALLO(L) | | W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L) ~SCHEMEL(L) YOUNGBLOOD(E) |
| KNIGH' ION (E) | | W/ Copies W/ Copies W/ Copies W/ Copies INTER'7AL DISTRIBUTION AEG TILET TECH REVIE'J w/DENTON A/T IND N vHENDRIE A; RIMES LIC ASST BRAIDIAN OGC, ROCM P-506A /SCHROEDER GAMMILL DIGGS (L) SALTZMAN MUNTZING/ STAFF /MACCARY KASTNER GEARIN (L) |
| W/ Copies~SCHEMEL(L) | | CASE KNIGHT BALLARD A;CULBOURNE (L) PLANS GIAMBUSSO PAWLICKI SPANGLER LEE (L) MCDONALD BOYD SHA0 MAIGRET (L) DUBE |
| YOUNGBLOOD(E)
| | / MOORE (L)(L'R) /STELLO ENVIRO SERVICE (L) |
| W/ Copies W/ Copies W/ Copies KNIEL(L)W/ Copies W/ Copies W/ Copies W/ Copies INTER'7AL DISTRIBUTION AEG TILET TECH REVIE'J w/DENTON A/T IND N vHENDRIE A; RIMES LIC ASST BRAIDIAN OGC, ROCM P-506A | | A)EYOUNG(U)(S'R) 4.0USTON A LLER SHEPPARD (E) INFO |
| /SCHROEDER GAMMILL DIGGS (L)SALTZMAN MUNTZING/ STAFF | | /SKOVHOLT (L) NOVAK DICKER SMITH (L) C. MILES P. COLLINS ROSS KNIGHTON TEETS (L) /R. Bernero |
| /MACCARY KASTNER GEARIN (L) | | .dPPOLITO YOUNGBLOOD WADE (E) / L. Rouse F & M REG OPR -TEDESCO REGAN WILLIAMS (E) |
| CASE KNIGHT BALLARD A;CULBOURNE (L) | | FILE & REGION (3) LONG PROJECT LDR MORRIS LAINAS WILSON 1 (L)584 316 -y . |
| PLANS GIAMBUSSO PAWLICKI SPANGLER LEE (L)MCDONALD BOYD SHA0 MAIGRET (L) | | STEELE BENAROYA HARI.ESS VOLINER EXTERNAL DISTRIBUTICN i, i vt - LOCAL PDR Harrisburg, Pa. l 1 - DTIE(A3ERNATHY) (1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY l - NSIC(3UCHANAN) 1- R.S chooneake r , CC,GT, D-323 1-GERALD LELLO'lC:-I 1 - ASLB(YCRE/SAYRE/ l-W. PENNINGTON, Pm E-201 GT BROOKHAVEN NAT. LA3 WCODARD/"H" ST. 1-CONSULTANT' S 1-AGMED(WAL*'IR KCCS"'I? |
| DUBE/ MOORE (L)(L'R)
| | 16 - CYS ACRS UOLDING NEWMARK/BLUME/AGBABIAN EM-C-427-GT l-GERALD ULRIKSCN. . .ORNL 7911070 7 0 0 g |
| /STELLO ENVIRO SERVICE (L) | | |
| A)EYOUNG(U)(S'R) 4.0USTON A LLER SHEPPARD (E) | | 6 N* Q .';$ , [3 Q -, ?lf] . - . . . |
| INFO/SKOVHOLT (L)
| | METROPOLITAN EDISON COMPANY PCST OFFICE BOX 542 READING PENNSYLVANI A 19603 TE LEPHONE 215 - 929 3601 September 10, 1973 Mr. A. Giambusso 8 Deputy Director for Reactor Projects United States Atomic Energy Comission S 4 Washington, DC 20545 kkC{ggg q |
| NOVAK DICKER SMITH (L)C. MILES P. COLLINS ROSS KNIGHTON TEETS (L)/R. Bernero.dPPOLITO YOUNGBLOOD WADE (E)/ L. Rouse F & M REG OPR-TEDESCO REGAN WILLIAMS (E) | | ~ |
| FILE & REGION (3) | |
| LONG PROJECT LDR WILSON (L)584 316 1-y .MORRIS LAINAS STEELE BENAROYA HARI.ESS VOLINER EXTERNAL DISTRIBUTICN i, i vt - LOCAL PDR Harrisburg, Pa. | |
| l 1 - DTIE(A3ERNATHY) | |
| (1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY l - NSIC(3UCHANAN) 1- R.S chooneake r , CC,GT, D-323 1-GERALD LELLO'lC:-I 1 - ASLB(YCRE/SAYRE/ | |
| l-W. PENNINGTON, Pm E-201 GT BROOKHAVEN NAT. LA3 WCODARD/"H" ST. | |
| 1-CONSULTANT' S 1-AGMED(WAL*'IR KCCS"'I? | |
| 16 - CYS ACRS UOLDING NEWMARK/BLUME/AGBABIAN EM-C-427-GT l-GERALD ULRIKSCN. . .ORNL 7911070 7 0 0 g | |
| _.....__. ....___, N*Q.';$ , [3 Q -, ?lf]6. - . . .METROPOLITAN EDISON COMPANY
| |
| .__ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _
| |
| PCST OFFICE BOX 542 READING PENNSYLVANI A 19603 TE LEPHONE 215 - 929 3601 September 10, 1973 Mr. A. Giambusso 8 Deputy Director for Reactor Projects S 4 United States Atomic Energy Comission kkC{ggg q Washington, DC 20545 SEP2~'U1 a,, 1194 | |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| THREE MILE ISLAND NUCLEAR STATION | | THREE MILE ISLAND NUCLEAR STATION SEP2 UNIT 1 - |
| --UNIT 1-I Com;e75'I DOCKET NO. 50-289 lf"'"%[
| | U1 a,, 1194 - |
| | DOCKET NO. 50-289 I Com;e75' I |
|
| |
|
| ==Dear Mr. Giambusso:== | | ==Dear Mr. Giambusso:== |
| | | C, lf"'"% C' |
| C, C', The August 14, 1973 letter written by Mr. H. G. Mangelsdort of the ACRS Comittee to the Honorable Dixy Lee Ray regarding the subject reactor, suggested that the Applicant assure himself that instrumentation for determining the course of potentially serious accidents, on a time scale that will permit approprlate emergency action, is provided at the station. | | [ |
| In additior, Applicant was asked to assure that appropriate calibration nethods and calculated bases for interpreting instrument responses are available. | | The August 14, 1973 letter written by Mr. H. G. Mangelsdort of the ACRS Comittee to the Honorable Dixy Lee Ray regarding the subject reactor, suggested that the Applicant assure himself that instrumentation for determining the course of potentially serious accidents, on a time scale that will permit approprlate emergency action, is provided at the station. In additior, Applicant was asked to assure that appropriate calibration nethods and calculated bases for interpreting instrument responses are available. |
| He have reviewed the situation and we are satisfied that: | | He have reviewed the situation and we are satisfied that: |
| (1) Adequate instrumentation has been provided; (2) Adequate calibration methods and procedures e.re available; and, (3) Calculated bases for interpreting instrument responses are available. | | (1) Adequate instrumentation has been provided; (2) Adequate calibration methods and procedures e.re available; and, (3) Calculated bases for interpreting instrument responses are available. |
| Enclosed is a listing of the instrumentation available to follow the course of an accident. The list includes references to the appropriate s the FSAR and the Technical Specifi-cations.g/8 k,'g Very truly yours, 1 SEP 21973'' | | Enclosed is a listing of the instrumentation available to follow the course of an accident. The list includes references to the appropriate s the FSAR and the Technical Specifi-cations. g/ |
| .. 2 h[A[k RMUL 1 J. G. Miller 9 ttgRK Vice President | | 8 k,' |
| ,#''uik 1584 317 r Enc.usure CC: Mr. W. A. Verrechi
| | g Very truly yours, 1 SEP 21973'' . . 2 9 RMUL 1 J. G. Miller |
| .
| | , h[A[k ttgRK Vice President r |
| '--._,...~;...,....*POST ACCIDENT INSTRUMENTATION
| | Enc.usure uik 1584 317 CC: Mr. W. A. Verrechi |
| .3d?. '* Lt M 1.Following an accident, the nuclear instrumentation will be available to confirm that the reactor is tripped. (see FSAR Section 7) 2.The balance of the reactor protection system instrumentation located outside of the primary shield will also be available, this in-cludes the measurement of reactor coolant pressure and reactor coolant temperature. (see FSAR Section 7) | | |
| '3.The qualification testing of the reactor protection system is discussed in Babcock & Wilcox Topical Report BAW 10003. Rev. 2.
| | .~;...,. . . |
| 4.We have additional post accident monitoring instrumentation which display, record and alarm in the control room. | | POST ACCIDENT INSTRUMENTATION .3d ?. '* Lt M |
| This instrumen-tation includes the following: | | : 1. Following an accident, the nuclear instrumentation will be available to confirm that the reactor is tripped. (see FSAR Section 7) |
| A.The reactor building radiation level, monitored by a high | | : 2. The balance of the reactor protection system instrumentation located outside of the primary shield will also be available, this in-cludes the measurement of reactor coolant pressure and reactor coolant temperature. (see FSAR Section 7) ' |
| -range gamma detegtor (channel DI-G8) which has a range of Ir/hr. to 1 X 10 r/hr. (see FSAR Section 11.4)
| | : 3. The qualification testing of the reactor protection system is discussed in Babcock & Wilcox Topical Report BAW 10003. Rev. 2. |
| B.The reactor building pressure with a range of 0-100 PSIG.(see FSAR Section 7.4.7) | | : 4. We have additional post accident monitoring instrumentation which display, record and alarm in the control room. This instrumen-tation includes the following: |
| C.The reactor building sump level. | | A. The reactor building radiation level, monitored by a high - |
| | range gamma detegtor (channel DI-G8) which has a range of Ir/hr. to 1 X 10 r/hr. (see FSAR Section 11.4) |
| | B. The reactor building pressure with a range of 0-100 PSIG. |
| | (see FSAR Section 7.4.7) |
| | C. The reactor building sump level. |
| These three measurements are qualified to operate folicwing an accident. | | These three measurements are qualified to operate folicwing an accident. |
| 5.There are 12 resistance temperature detectors located in different areas of the reactor building. These resistance temperature detectors are expected to provide information on reactor building temperature after an accident. | | : 5. There are 12 resistance temperature detectors located in different areas of the reactor building. These resistance temperature detectors are expected to provide information on reactor building temperature after an accident. |
| 6.In addition, we have outside the reactor building the following instruments which indicate in the control room: | | : 6. In addition, we have outside the reactor building the following instruments which indicate in the control room: |
| A.High Pressure Injection flow (see FSAR Figure 6.2) | | A. High Pressure Injection flow (see FSAR Figure 6.2) |
| B.Low Pressure Injection flow (see FSAR Figure 6.2) | | B. Low Pressure Injection flow (see FSAR Figure 6.2) |
| C.Low Pressure Injection pump suction temperature (see FSAR Figure 6.2) | | C. Low Pressure Injection pump suction temperature (see FSAR Figure 6.2) |
| D.Decay heat closed cycle temperature Table 3.5-1 (Instrument Operating Conditions) of Technical Speci-fication 3.5.1 lists the requirements for reactor startup or critical operation. Table 4.1-1 (Instrument Surveillance Requirements) of Tech. | | D. Decay heat closed cycle temperature Table 3.5-1 (Instrument Operating Conditions) of Technical Speci-fication 3.5.1 lists the requirements for reactor startup or critical operation. Table 4.1-1 (Instrument Surveillance Requirements) of Tech. |
| Spec. 4.1 indicates the calibration schedule for the instrumentation mentioned above. | | Spec. 4.1 indicates the calibration schedule for the instrumentation mentioned above. |
| 1584 318}} | | 1584 318}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M0721999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Pass Dates
ML20217D8361999-10-11011 October 1999
Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999
ML20217F8271999-10-0707 October 1999
Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans
ML20212L1831999-10-0101 October 1999
Responds to Recent Ltr to Wd Travers Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Performance of Millstone to Ensure Adequate Protection to Public Health
ML20212L2081999-10-0101 October 1999
Responds to Recent Ltrs to President Wj Clinton,Chairman Jackson & Commissioners & Wd Travers,Expressing Concerns Re Millstone NPPs & Continued Lack of Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance
ML20212K1241999-10-0101 October 1999
Responds to Recent Ltrs to Chairman Jackson,Commissioners & Wd Travers,Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performace of Millstone to Ensure That Public Health & Safety,Adequately Protected
ML20212L1971999-10-0101 October 1999
Responds to Recent Ltr to Chairman Jackson & Commissioners Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Continues to Monitor Plant Performance to Ensure Public Health & Safety
ML20212J9991999-10-0101 October 1999
Responds to Recent Ltr to President Clinton,H Clinton, Chairman Jackson &/Or Wd Travers Expressing Concern Re Millstone Npps.Nrc Continues to Monitor Performance of Plant to Ensure That Public Health & Safety Adequately Protected
ML20212L0061999-10-0101 October 1999
Discusses GL 97-06 Issued by NRC on 971231 & Gpu Response for Three Mile Island .Staff Reviewed Response & Found No New Concerns with Condition of SG Internals or with Insp Practices Used to Detect Degradation of SG Internals
ML20212L2171999-10-0101 October 1999
Responds to Recent Ltr to President Wj Clinton,Chairman Jackson & Commissioners,Wd Travers & Ferc,Expressing Concerns Re Millstone NPPs & Continued Lack of Emergency Mgt Plan for Eastern Long Island
ML20212K8771999-09-30030 September 1999
Informs of Completion of mid-cycle PPR of Three Mile Island on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Provides Historical Listing of Plant Issues & Insp Schedule
ML20212K8551999-09-30030 September 1999
Informs That During 990921 Telcon Between P Bissett & F Kacinko,Arrangements Were Made for Administration of Licensing Exams at Facility During Wk of 000214.Outlines Should Be Provided to NRC by 991122
ML20216J6581999-09-28028 September 1999
Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
ML20212J0011999-09-27027 September 1999
Forwards Insp Rept 50-289/99-07 on 990828.No Violations Noted
ML20212E1971999-09-16016 September 1999
Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions
ML20212A2101999-09-13013 September 1999
Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2
ML20216G4151999-09-0909 September 1999
Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans
ML20211M5861999-09-0202 September 1999
Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld
ML20211M6591999-09-0101 September 1999
Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error
ML20211L2401999-09-0101 September 1999
Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates
ML20211H3731999-08-27027 August 1999
Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl
ML20211H4001999-08-27027 August 1999
Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl
ML20211K2391999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj
ML20211H5041999-08-20020 August 1999
Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld
05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999
Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface
ML20211A4261999-08-19019 August 1999
Forwards Insp Rept 50-289/99-04 on 990606-0717.Two Severity Level 4 Violations Occurred & Being Treated as Noncited Violations
ML20211H3571999-08-19019 August 1999
Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019
ML20211A3931999-08-12012 August 1999
Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports
ML20210R4691999-08-11011 August 1999
Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages
ML20210N7601999-08-10010 August 1999
Informs That NRC Staff Reviewed Applications Dtd 990629, Which Requested Review & Approval to Allow Authority to Possess Radioactive Matl Without Unit Distinction Between Units 1 & 2.Forwards RAI Re License Amend Request 285
ML20210N7191999-08-0606 August 1999
Forwards Notice of Partial Denial of Amend to FOL & Opportunity for Hearing Re Proposed Change to TS 3.1.12.3 to Add LCO That Would Allow Continued HPI Operation
ML20210L3831999-07-30030 July 1999
Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage
ML20210K7371999-07-30030 July 1999
Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46
ML20210L1151999-07-28028 July 1999
Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1
05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999
Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section
ML20216D4001999-07-22022 July 1999
Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999
ML20210B8231999-07-21021 July 1999
Forwards Exemption from Certain Requirements of 10CFR50.54(w) for Three Mile Island Nuclear Station,Unit 2 in Response to Licensee Application Dtd 990309,requesting Reduction in Amount of Insurance for Unit to Amount Listed
ML20210G9471999-07-15015 July 1999
Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl
ML20209H9401999-07-15015 July 1999
Forwards Copy of Environ Assessment & Findings of No Significant Impact Re Application for Exemption Dtd 990309. Proposed Exemption Would Reduce Amount of Insurance for Onsite Property Damage Coverage as Listed
ML20209G2451999-07-15015 July 1999
Advises That Suppl Info in Support of Proposed License Transfer & Conforming Adminstrative License Amends,Submitted in & Affidavit,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20212K1701999-07-13013 July 1999
Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident
ML20216D9861999-07-12012 July 1999
Forwards RAI Re 981019 Application Request for Review & Approval of Operability & SRs for Remote Shutdown Sys. Response Requested within 30 Days of Receipt of Ltr
ML20209G5861999-07-0909 July 1999
Forwards Insp Rept 50-289/99-05 on 990510-28.No Violations Noted
ML20209F2571999-07-0909 July 1999
Forwards Staff Evaluation Rept of Individual Plant Exam of External Events Submittal on Three Mile Nuclear Station, Unit 1
ML20209D8451999-07-0808 July 1999
Forwards Insp Rept 50-289/99-06 on 990608-11.No Violations Noted.Overall Performance of ERO Very Good & Demonstrated, with Reasonable Assurance,That Onsite Emergency Plans Adequate & That Util Capable of Implementing Plan
ML20209D6291999-07-0808 July 1999
Forwards Notice of Withdrawal & Corrected TS Pages 3-21 & 4-9 for Amend 211 & 4-5a,4-38 & 6-3 for Amend 212,which Was Issued in Error.Amends Failed to Reflect Previously Changes Granted by Amends 203 & 204
ML20209D5141999-07-0808 July 1999
Forwards RAI Re 981019 Application & Suppl ,which Requested Review & Approval of Revised Rc Allowable Dose Equivalent I-131 Activity Limit with Max Dose Equivalent Limit of 1.0 Uci/Gram.Response Requested within 30 Days
05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999
Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public
ML20196J3981999-07-0101 July 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl
ML20209C1131999-07-0101 July 1999
Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217D8361999-10-11011 October 1999
Provides NRC with Summary of Activities at TMI-2 During 3rd Quarter of 1999
ML20217F8271999-10-0707 October 1999
Forwards Pmpr 99-13, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990828- 0924.Diskette Containing Pmpr in Wordperfect 8 Is Encl. All Variances Are Expressed with Regard to Current Plans
ML20216J6581999-09-28028 September 1999
Provides Info as Requested of Licensees by NRC in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams
ML20212E1971999-09-16016 September 1999
Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions
ML20212A2101999-09-13013 September 1999
Forwards Rev 3 of Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2, Including Changes Made During 1998.Description of Changes Provided on Page 2
ML20216G4151999-09-0909 September 1999
Forwards Pmpr 99-12, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting Period 990731- 0827.All Variances Expressed with Regard to Current Operations Plans
ML20211M5861999-09-0202 September 1999
Forwards non-proprietary & Proprietary Response to NRC 990708 RAI Re TS Change Request 272,reactor Coolant Sys Coolant Activity.Proprietary Encl Withheld
ML20211M6591999-09-0101 September 1999
Forwards Errata Page to 990729 Suppl to TS Change Request 274,to Reflect Proposed Changes Requested by . Page Transmitted by Submitted in Error
ML20211L2401999-09-0101 September 1999
Submits Response to NRC AL 99-02, Operator Reactor Licensing Action Estimates
ML20211H3731999-08-27027 August 1999
Responds to NRC 990810 RAI Re TMI LAR 285 & TMI-2 LAR 77 Re Changes Reflecting Storage of TMI-1 Radioactive Matls in TMI-2 Facility.Revised License Page mark-up,incorporating Response,Encl
ML20211H4001999-08-27027 August 1999
Responds to NRC 990810 RAI Re TMI-1 LAR 285 & TMI-2 LAR 77 Re Changes to Clarify Authority to Possess Radioactive Matls Without Unit Distinction.Revised License Page mark-up, Incorporating Response Encl
ML20211K2391999-08-23023 August 1999
Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj
05000289/LER-1999-007, Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface1999-08-20020 August 1999
Forwards LER 99-007-01 Re Increasing Failure Rate of ESAS Relays.Rept Supplements Preliminary Info Re Determination of Root Cause & Long Term Corrective Actions.Changes Made for Supplement Are Indicated in Bold Typeface
ML20211H5041999-08-20020 August 1999
Forwards Proprietary & non-proprietary Rept MPR-1820,rev 1, TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis. Affidavit Encl.Proprietary Rept Wihheld
ML20211H3571999-08-19019 August 1999
Forwards Itemized Response to NRC 990712 RAI Re TS Change Request 248 Re Remote Shutdown Sys,Submitted on 981019
ML20211A3931999-08-12012 August 1999
Requests NRC Concurrence with Ongoing Analytical Approach as Described in Attachment,Which Is Being Utilized by Gpu Nuclear to Support Detailed License Amend Request to Revise Design Basis for TMI-1 Pressurizer Supports
ML20210R4691999-08-11011 August 1999
Forwards Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2.Update 3 Revises SAR to Reflect Current Plant Configuration & Includes Minor Editorial Changes & Corrections.Revised Pages on List of Effective Pages
ML20210L3831999-07-30030 July 1999
Responds to NRC 990617 RAI Re OTSG Kinetic Expansion Region Insp Acceptance Criteria That Was Used for Dispositioning Indications During Cycle 12 Refueling (12R) Outage
ML20210K7371999-07-30030 July 1999
Forwards Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp LOCA, Which Corrects Evaluation Model for Mk-B9 non- Mixing Vane Grid Previously Reported in Util to Nrc,Per 10CFR50.46
ML20210L1151999-07-28028 July 1999
Confirms Two Senior Management Changes Made within Amergen Energy Co,Per Proposed License Transfer & Conforming Administrative License Amends for TMI-1
05000289/LER-1999-009, Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section1999-07-22022 July 1999
Forwards LER 99-009-00 Re 990626 Event Involving Partial Loss of Offsite Power & Subsequent Automatic Start of EDG 1A.Commitments Made by Util Are Contained in long-term Corrective Actions Section
ML20216D4001999-07-22022 July 1999
Provides Summary of Activities at TMI-2 During 2nd Quarter of 1999
ML20210G9471999-07-15015 July 1999
Forwards Pmpr 99-10, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990605- 0702.Diskette Containing Pmpr in Wordperfect 8 Format Is Also Encl
ML20212K1701999-07-13013 July 1999
Submits Concerns Re Millstone & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Nrc Should Provide Adequate Emergency Planning in Case of Radiological Accident
05000289/LER-1999-008, Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public1999-07-0202 July 1999
Forwards LER 99-008-00 Re Discovery of Degraded But Operable Condition of RB Emergency Cooling Sys.Condition Did Not Adversely Affect Health & Safety of Public
ML20196J3981999-07-0101 July 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure for TMI-1 Encl
ML20209C1131999-07-0101 July 1999
Forwards Signed Agreement as Proposed in NRC Requesting Gpu Nuclear Consent in Incorporate TMI-1 Thermo Lag Fire Barrier Final Corrective Action Completion Schedule Commitment of 000630 Into Co Modifying License
ML20196J7651999-06-29029 June 1999
Provides Updated Info Re Loss of Feedwater & Loss of Electric Power Accident Analyses to Support TS Change Request 279 Re Core Protection Safety Limit,As Discussed at 990616 Meeting
ML20196J7701999-06-29029 June 1999
Forwards LAR 285 for License DPR-50,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-1 License to Amergen,Radioactive Matls May Continue to Be Moved Between TMI-1 & TMI-2 Units
ML20209C0391999-06-29029 June 1999
Forwards LAR 77 to License DPR-73,clarifying Authority to Possess Radioactive Matls Without Unit Distinction,So That After Transfer of TMI-2 License to Amergen,Radioactive Matl May Continue to Be Moved Between TMI-1 & TMI-2 Units
ML20196G2061999-06-23023 June 1999
Requests That NRC Update Current Service Lists to Reflect Listed Personnel Changes That Occurred at TMI
05000289/LER-1999-006, Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements1999-06-23023 June 1999
Forwards LER 99-006-00,providing Complete Description,Extent of Condition & Actions Taken in Association with Determination of Inability of Pressurizer Support Bolts to Meet FSAR Requirements
ML20196D2171999-06-17017 June 1999
Forwards Pmpr 99-9, CNWRA Program Manager Periodic Rept on Activities of CNWRA, for Fiscal Reporting period,990508- 0604.New Summary Personnel Table Was Added to Rept Period.Matl Scientist Joined Staff Period
ML20196A0431999-06-15015 June 1999
Providess Notification That Design Verification Activities Related to Calculations Supporting Analytical Values Identified in Gpu Nuclear Ltr to NRC Has Been Completed
05000289/LER-1999-004, Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT1999-06-0909 June 1999
Forwards LER 99-004-00,re Discovery of Emergency FW Pump Bearing Failure During Performance of Oil Change on 990510. Event Was Determined Reportable IAW 10CFR50.73,since Pump Was Determined to Be Inoperable Longer than TS AOT
ML20212K2541999-06-0808 June 1999
Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident
ML20212K2671999-06-0808 June 1999
Submits Concerns Re Millstone NPP & Continued Lack of Emergency Mgt Plan for Eastern Long Island.Requests That NRC Provide Adequate Emergency Planning in Case of Radiological Accident
ML20195E2751999-06-0404 June 1999
Informs That PCTs & LOCA Lhr Limits Submitted in Util Ltr for LOCA Reanalysis Performed in Support of TMI-1 20% Tube Plugging Amend Request Have Been Revised.Revised PCT & LOCA Lhr Limit Values Are Provided on Encl Table 1
ML20195E3281999-06-0404 June 1999
Forwards Application for Amend to License DPR-50,modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions
ML20195C5721999-06-0202 June 1999
Forwards Description of Gpu Nuclear Plans for Corrective Actions for 1 H Fire Barriers in Fire Zones AB-FZ-3,AB-FZ-5, AB-FZ-7,FH-FZ-2 & Previous Commitments for Fire Zones CB-FA-1 & FH-FZ-6
ML20207E2561999-05-25025 May 1999
Submits 30-day Written Rept on Significant PCT Change in ECCS Analyses at TMI-1
ML20195B2461999-05-21021 May 1999
Forwards Itemized Response to NRC 990506 RAI for TS Change Request 279 Re Core Protection Safety Limit
ML20206R6461999-05-13013 May 1999
Forwards Rev 39 of Modified Amended Physical Security Plan for TMI
05000289/LER-1999-003, Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC1999-05-0707 May 1999
Forwards LER 99-003-00, Discovery of Condition Outside UFSAR Design Basis for CR Habitability, Which Was Determined Reportable on 990310.Rept Is Being Submitted Four Weeks Later than Required,Per Discussion with NRC
ML20206K6301999-05-0707 May 1999
Provides Addl Info Re TMI-1 LOFW Accident re-analysis Assumptions for 20% Average SG Tube Plugging as Discussed on 990421
ML20206H0781999-04-30030 April 1999
Forwards Rev 0 to 1092, TMI Emergency Plan. Summary of Changes Encl
ML20206J4811999-04-30030 April 1999
Provides Summary of Activities at TMI-2 During First Quarter of 1999.TMI-2 RB Was Not Inspected During Quarter.Routine Radiological Surveys of Auxiliary & Fuel Handling Bldgs Did Not Identify Any Significant Adverse Trends
ML20206E4121999-04-27027 April 1999
Requests That TS Change Request 257 Be Withdrawn
ML20206C5211999-04-23023 April 1999
Requests Mod to Encl Indemnity Agreement Number B-64,on Behalf of Gpu & Affiliates,Meed,Jcpl,Penelec & Amergen Energy Co,Llc.Ltr Supersedes & Withdraws 990405 Request Submitted to NRC
ML20206C8261999-04-22022 April 1999
Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21
1999-09-09
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059H5351990-09-10010 September 1990
Forwards Encls 1-3 of Generic Ltr 90-07 Re Operator Licensing Exam Schedule
ML20059G0641990-08-31031 August 1990
Advises That Util Agreed to Revised Frequency of Once Every 12 Months for Corrective Actions Audits Per Tech Spec Change Request 65 Based on 900718 & 19 Discussions
ML20059F1691990-08-30030 August 1990
Requests Exemption from Requirements of 10CFR50,App J, Section III.D.1(a) for Facility Re Schedule Requirements for Connecting Type a Testing w/10-yr Inservice Insp Interval, Per 10CFR50.12(a)(2)
ML20064A4661990-08-30030 August 1990
Responds to 900803 SALP Rept 50-289/89-99.TMI Does Not Expect to Be Lead Plant for Installation of Advanced Control Sys.Maint Backlog Goals Established.Info on Emergency Preparedness & Engineering/Technical Support Encl
ML20059C8791990-08-29029 August 1990
Forwards TMI-1 Semiannual Effluent & Release Rept for Jan - June 1990, Including Executive Summary of Effluent Release Rept,Disposal & Effluent Release Data & Assessment of Radiation Doses.No Changes to ODCM for Reporting Period
ML20059D5491990-08-29029 August 1990
Responds to NRC Re Notice of Violation & Proposed Imposition of Civil Penalty Re Personnel Inattentiveness & Failure of Site Managers to Correct Condition.Shift & Immediate Supervisor Discharged
ML20059C7851990-08-27027 August 1990
Forwards Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility, Updating Minor Changes to Pages 6,8,9 & 13
ML20059C1091990-08-24024 August 1990
Forwards Rev 6 to Physical Security Contingency Plan.Rev Withheld
ML20059B8251990-08-24024 August 1990
Forwards Payment of Civil Penalty in Amount of $50,000,per NRC
ML20056B4651990-08-20020 August 1990
Corrects Statement Made in 900716 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Rosemount Transmitters. Identified That Only Half of Operating Crews Provided W/ Briefing on Bulletin
ML20058Q1851990-08-17017 August 1990
Requests That Distribution List for TMI-2 Correspondence Be Updated to Be Consistent W/Recently Implemented Organizational Changes.Ee Kintner,Mb Roche & Wj Marshall Should Be Deleted
ML20058Q1821990-08-13013 August 1990
Advises That Util Will No Longer Provide Annual Update to Dewatering Sys for Defueling Canisters Sys Description,Per NRC .W/Completion of Defueling & Shipment of All Defueling Canisters Offsite,Sys Has Been Deactivated
ML20058Q1721990-08-13013 August 1990
Forwards TMI-2 Effluent & Offsite Dose Rept,First Quarter 1990, Update
ML20058M7201990-08-0303 August 1990
Forwards Rev 2 to TER 3232-019, Div Technical Evaluation Rept for Processed Water Disposal Sys. Mods Include Elimination of Pelletizer & Relocation of Druming Station to Discharge of Blender/Dryer
ML20055J4581990-07-27027 July 1990
Responds to Violations Noted in Insp Rept 50-289/90-10. Corrective Actions:Missing Support Brace on Cable Tray Support Found & Corrected
ML20055J4561990-07-27027 July 1990
Advises That Info Contained in Generic Ltr 90-06,not Applicable to Current Nonoperating & Defueled Condition of Facility.Generic Ltr Will Be Reevaluated,If Decision Made to Restart Facility
ML20055H6901990-07-20020 July 1990
Forwards Rev 25 to TMI-2 Organization Plan for NRC Review & Approval.Rev Proposes Consolidation of Plant Operations & Maint Sections Into Plant Operation & Maint Section
ML20055G4431990-07-19019 July 1990
Forwards Rev 12 to 990-1745, TMI-1 Fire Hazards Analysis Rept & Update 9 to FSAR for TMI-1
ML20055G8781990-07-19019 July 1990
Discusses Compliance W/Reg Guide 1.97 Re Containment High Range Radiation Monitors,Per 900507-11 Insp.Physical Separation of Power Cables & Required Isolation Will Be Provided to Satisfy Reg Guide Category 1 Requirements
ML20055F9601990-07-11011 July 1990
Forwards, 1990 TMI Nuclear Station Annual Emergency Exercise Scenario to Be Conducted on 900912.W/o Encl
ML20044A9531990-07-0909 July 1990
Forwards Util Response to Weaknesses Identified in Maint Team Insp Rept 50-289/89-82.Corrective Actions:Engineering Personnel Reminded to Assure Documented Approval Obtained Prior to Proceeding W/Work
ML20055E0481990-07-0505 July 1990
Documents Action Taken by Util to Improve Heat Sink Protection Sys & Current Status of Sys.Main Feedwater Logic Circuits Modified Prior to Startup from 8R Outage to Eliminate Potential for Inadvertent Isolation
ML20055E0011990-07-0202 July 1990
Forwards Revs 1 & 2 to Topical Rept 067, TMI-1 Cycle 8 Core Operating Limits Rept, Per Tech Spec 6.9.5.4
ML20055C9971990-06-28028 June 1990
Forwards Rev 27 to Physical Security Plan.Rev Withheld
ML20055D2071990-06-28028 June 1990
Forwards Certification of TMI-1 Simulation Facility,Per 10CFR55.45.b.5.Resumes of Personnel Involved Encl. Resumes Withheld (Ref 10CFR2.790(a)(6))
ML20055D0861990-06-25025 June 1990
Documents Deviation from Requirements of Reg Guide 1.97,per Insp on 900507-11.Based on Most Limiting Analysis,Existing Range of 0-1,200 Psi Sufficient.Deviation Consistent W/B&W Owners Group Task Force Evaluation of Reg Guide
ML20043H4031990-06-18018 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issue Resolved W/Imposition of Requirements or Corrective Actions.
ML20043H4851990-06-18018 June 1990
Forwards Application for Amend to License DPR-50,consisting of Tech Spec Change Request 179
ML20043F9921990-06-11011 June 1990
Forwards Listing of Exam Ref Matl Sent on 900601 in Response to 900505 Ltr
ML20043F0661990-06-0404 June 1990
Forwards Inservice Insp Data Rept for Period 880816-900304. Owner Rept for Repairs or Replacements Performed on ASME Section XI Class 1 & 2 Components,Also Encl
ML20055C9041990-05-23023 May 1990
Advises That App a to Rept Is Set of Recommendations from Safety Advisory Board on Possible Research Opportunities
ML20043B2391990-05-18018 May 1990
Revises Commitments in Encl Met Ed 800430 Ltr Re QA of Diesel Generator Fuel Oil.Requirement for QC Review for Acceptability Prior to Filling Diesel Generator Fuel Oil Storage Tanks Deleted from Procedure
ML20043A5441990-05-16016 May 1990
Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project
ML20043A5311990-05-15015 May 1990
Responds to Violations Noted in Insp Rept 50-289/89-82. Corrective Actions:Periodic Insp Program Established Utilizing Checklist for Stored Equipment & Existing Tool Rooms Will Be Purged of Controlled or Unneeded Matls
ML20043A2321990-05-11011 May 1990
Forwards TMI-1 Reactor Bldg 15-Yr Tendon Surveillance (Insp Period 5) Technical Rept 069.Evaluations Conclude That Test & Insp Results Demonstrate TMI-1 Reactor Bldg post- Tensioning Sys in Good Condition
ML20042G2741990-05-0404 May 1990
Forwards Semiannual Update of Projects Listed in Categories A,B & C of long-range Planning Program Integrated Schedule
ML20012F2621990-04-0202 April 1990
Responds to Violation Noted in Insp Rept 50-289/89-26. Corrective Actions:Util Policy of Shift Supervisor Involvement in Bypassing & Resetting Safety Sys Expanded to Include Shutdown Conditions & Technicians Briefed
ML20012F2611990-04-0202 April 1990
Provides Supplemental Response to Station Blackout Rule. Target Reliability of 0.975 Chosen for Emergency Diesel Generators.Diesel Generator Reliability Program May Change Based on Final Resolution of Generic Issue B-56
ML20012F2731990-03-30030 March 1990
Confirms 900328 Conversations & Provides Technical Basis for Planned Actions to Correct Present Power Limitation Due to High Steam Generator Secondary Side Differential Pressure. Main Turbine Will Be Tripped from 80% Power
ML20042D8281990-03-23023 March 1990
Fulfills Requirements of Tech Spec Section 4.19.5.a Re once-through Steam Generator Tubes post-inservice Insp Rept for Unscheduled Outage 8U-1
ML20012D7001990-03-22022 March 1990
Forwards Util Response to Generic Ltr 90-01 Re NRC Regulatory Impact Survey.Site Mgt & Staff Hour Categories Added to Response
ML20012D7121990-03-21021 March 1990
Forwards Rev 0 to TMI-1 Cycle 8 Core Operating Limits Rept.
ML20012C4771990-03-12012 March 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47, 'Safety Implication of Control Sys in LWR Nuclear Power Plants,' Per 10CFR50.54(f). Current Design Adequate W/O Addl Tech Specs
ML20012B8241990-03-12012 March 1990
Forwards Application for Tech Spec Change Request 199 to License DPR-50,revising Tech Specs Re Steam Generator Tube Insp Requirements
ML20011F5251990-02-23023 February 1990
Documents Interpretation of Tech Spec 5.3.1.1 Re Design Features of Fuel Assemblies in Light of Issuance of Generic Ltr 90-02.Tech Spec Change Request Re Utilization of Dummy Fuel Rods or Open Water Channels Will Be Filed by 900420
ML20055C3931990-02-23023 February 1990
Documents Interpretation of Tech Spec 4.19.5.a Re once- Through Steam Generator Tube post-inservice Insp Rept for Refueling Interval 8R.Total of Eight Tubes Removed from Svc by Plugging
ML20011F6651990-02-22022 February 1990
Forwards Updated Status Summary of Consideration of TMI-1 PRA Recommendations as of 891231.Changes to Torque Switch Settings for DH-V-4A & B Will Be Implemented in Refueling Outage 8 Re Closing Against High Differential Pressure
ML20006C2901990-01-26026 January 1990
Provides Addl Info Supporting Deferral of Seismic Qualification Util Group Walkdowns to 10R Outage.Performance of Walkdowns Provide Proper Scheduling & Priority for Resolution of USI A-46 for TMI-1
ML20011E1221990-01-26026 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Audit Rept Determined That Operation of Decay Heat Closed Cooling Water Sys Consistent W/Design Basis Documents
ML19354E8601990-01-25025 January 1990
Requests Approval for Use of B&W Steam Generator Plugs Mfg W/Alternate Matl (nickel-base Alloy/Alloy 600).Alloy 600 Has Superior Corrosion Resistance to Primary Water Stress Corrosion Cracking
1990-09-10
[Table view] |
Text
_ . - - . .
. AEC :3U'" ION FOR PART 50 DCCKET m AL (TCiPORARY F0EM) CONTROL NO: 7085 FILE: -
FROM: DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Metropolitan Edison Company Reading Pa. 19603 9-10-73 9-21-73 X J. G. Miller TO: ORIG CC OTHER SENT AEC PDR X A. Giambusso 1 signed SENT LOCAL PDR X CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
XX 1 '5'072'89 %
w --
DESCRIPTICN: ENCLOSURES:
Ltr re ACRS 8-14-73 ler. . . . . . . . Trans the fol- Post Accident Instrumentation- instrumentation lowing: for determining the course of potentially serious accident ACKNOWLEDGED DO NOT REMOVE PLANT NAME: Three Mile Island Unit-1 ( l cys rec'd )
FOR ACTICN/INFORMATION 9-21-73 GC BUTLER (L) dCBJENCER(L) ZIEMANN(L) REGAN(E)
W/ Copies W/ 2 Copies W/ Copies W/ Copies CLARK (L) STOLZ(L) DICKER (E)
W/ Copies W/ Copies W/ Copies W/ Copies COLLER(L) VASSALLO(L) KNIGH' ION (E)
W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L) ~SCHEMEL(L) YOUNGBLOOD(E)
W/ Copies W/ Copies W/ Copies W/ Copies INTER'7AL DISTRIBUTION AEG TILET TECH REVIE'J w/DENTON A/T IND N vHENDRIE A; RIMES LIC ASST BRAIDIAN OGC, ROCM P-506A /SCHROEDER GAMMILL DIGGS (L) SALTZMAN MUNTZING/ STAFF /MACCARY KASTNER GEARIN (L)
CASE KNIGHT BALLARD A;CULBOURNE (L) PLANS GIAMBUSSO PAWLICKI SPANGLER LEE (L) MCDONALD BOYD SHA0 MAIGRET (L) DUBE
/ MOORE (L)(L'R) /STELLO ENVIRO SERVICE (L)
A)EYOUNG(U)(S'R) 4.0USTON A LLER SHEPPARD (E) INFO
/SKOVHOLT (L) NOVAK DICKER SMITH (L) C. MILES P. COLLINS ROSS KNIGHTON TEETS (L) /R. Bernero
.dPPOLITO YOUNGBLOOD WADE (E) / L. Rouse F & M REG OPR -TEDESCO REGAN WILLIAMS (E)
FILE & REGION (3) LONG PROJECT LDR MORRIS LAINAS WILSON 1 (L)584 316 -y .
STEELE BENAROYA HARI.ESS VOLINER EXTERNAL DISTRIBUTICN i, i vt - LOCAL PDR Harrisburg, Pa. l 1 - DTIE(A3ERNATHY) (1)(2)(10)-NATIONAL LAB'S 1-PDR-SAN /LA/NY l - NSIC(3UCHANAN) 1- R.S chooneake r , CC,GT, D-323 1-GERALD LELLO'lC:-I 1 - ASLB(YCRE/SAYRE/ l-W. PENNINGTON, Pm E-201 GT BROOKHAVEN NAT. LA3 WCODARD/"H" ST. 1-CONSULTANT' S 1-AGMED(WAL*'IR KCCS"'I?
16 - CYS ACRS UOLDING NEWMARK/BLUME/AGBABIAN EM-C-427-GT l-GERALD ULRIKSCN. . .ORNL 7911070 7 0 0 g
6 N* Q .';$ , [3 Q -, ?lf] . - . . .
METROPOLITAN EDISON COMPANY PCST OFFICE BOX 542 READING PENNSYLVANI A 19603 TE LEPHONE 215 - 929 3601 September 10, 1973 Mr. A. Giambusso 8 Deputy Director for Reactor Projects United States Atomic Energy Comission S 4 Washington, DC 20545 kkC{ggg q
~
SUBJECT:
THREE MILE ISLAND NUCLEAR STATION SEP2 UNIT 1 -
U1 a,, 1194 -
DOCKET NO. 50-289 I Com;e75' I
Dear Mr. Giambusso:
C, lf"'"% C'
[
The August 14, 1973 letter written by Mr. H. G. Mangelsdort of the ACRS Comittee to the Honorable Dixy Lee Ray regarding the subject reactor, suggested that the Applicant assure himself that instrumentation for determining the course of potentially serious accidents, on a time scale that will permit approprlate emergency action, is provided at the station. In additior, Applicant was asked to assure that appropriate calibration nethods and calculated bases for interpreting instrument responses are available.
He have reviewed the situation and we are satisfied that:
(1) Adequate instrumentation has been provided; (2) Adequate calibration methods and procedures e.re available; and, (3) Calculated bases for interpreting instrument responses are available.
Enclosed is a listing of the instrumentation available to follow the course of an accident. The list includes references to the appropriate s the FSAR and the Technical Specifi-cations. g/
8 k,'
g Very truly yours, 1 SEP 21973 . . 2 9 RMUL 1 J. G. Miller
, h[A[k ttgRK Vice President r
Enc.usure uik 1584 317 CC: Mr. W. A. Verrechi
.~;...,. . .
POST ACCIDENT INSTRUMENTATION .3d ?. '* Lt M
- 1. Following an accident, the nuclear instrumentation will be available to confirm that the reactor is tripped. (see FSAR Section 7)
- 2. The balance of the reactor protection system instrumentation located outside of the primary shield will also be available, this in-cludes the measurement of reactor coolant pressure and reactor coolant temperature. (see FSAR Section 7) '
- 3. The qualification testing of the reactor protection system is discussed in Babcock & Wilcox Topical Report BAW 10003. Rev. 2.
- 4. We have additional post accident monitoring instrumentation which display, record and alarm in the control room. This instrumen-tation includes the following:
A. The reactor building radiation level, monitored by a high -
range gamma detegtor (channel DI-G8) which has a range of Ir/hr. to 1 X 10 r/hr. (see FSAR Section 11.4)
B. The reactor building pressure with a range of 0-100 PSIG.
(see FSAR Section 7.4.7)
C. The reactor building sump level.
These three measurements are qualified to operate folicwing an accident.
- 5. There are 12 resistance temperature detectors located in different areas of the reactor building. These resistance temperature detectors are expected to provide information on reactor building temperature after an accident.
- 6. In addition, we have outside the reactor building the following instruments which indicate in the control room:
A. High Pressure Injection flow (see FSAR Figure 6.2)
B. Low Pressure Injection flow (see FSAR Figure 6.2)
C. Low Pressure Injection pump suction temperature (see FSAR Figure 6.2)
D. Decay heat closed cycle temperature Table 3.5-1 (Instrument Operating Conditions) of Technical Speci-fication 3.5.1 lists the requirements for reactor startup or critical operation. Table 4.1-1 (Instrument Surveillance Requirements) of Tech.
Spec. 4.1 indicates the calibration schedule for the instrumentation mentioned above.
1584 318
