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| {{#Wiki_filter:ACCE REGULATORY NFORMATION DISTRIBUTION SY TEM (R N NBRNB107210416 DOC IDS)FACILE:50'15 Donald C~Cook N'4 1 07/15 NOTAR'xcKD) | | {{#Wiki_filter:REGULATORY NFORMATION DISTRIBUTION SY TEM (R IDS) |
| NO 50 316 Donald C C k.N ,ower Planti Unit fr Indiana S, p5 H.NAME<AUTHOR AF FILIATION: | | ACCE N NBRNB107210416 DOC '4 1 07/15 NOTAR'xcKD) NO FACILE:50'15 Donald C~ Cook N ,ower Planti Unit fr Indiana S, p5 50 316 Donald C C k. N 'g Uni t 2'z Indi ane L 05p0031 6 H.NAME< AUTHOR AF FILIATION: |
| 'g Uni t 2'z Indi ane L 05p0031 6 HUNTERrR>>.S< | | HUNTERrR>>.S< Indiana L Michi an N |
| Indiana L Michi an DENTON O'o N I Of f ice of Nuclear Reactor" R l ti egu a onr Director~SUBJECT':." Forwards info rei enginee'ring, descri ba k o d i fo details for=reactor" vessel e c or" vessel hea ventsrfn response, to NUREG DISTRIBUTIO N CODE~)A046S COPIKS RECElIVED: | | DENTON O' I o f ice Of of Nuclear Reactor" R egu l a ti onr Director~ |
| TITLES=Response>>to NURKG<<0737 N:LiTR ENCL]'IZE: '~'NUREG<<0660 TMI Acti'P on'an Rgmts'OL's) | | SUBJECT':." Forwards info rei enginee'ring, descri ba k o d i fo details for=reactor" e c or" vessel hea ventsrfn response, to NUREG DISTRIBUTION CODE~) A046S COPIKS RECElIVED::LiTR ENCL Acti on 'P |
| NOTESt-ILE'.3 copies" al 1 mat er el~en copies of all matet'ial to ILK', 05000315 05000316" RECIPIENT ID>>CODE'/NAMEI ACTION$: ORB 0 f BC05>>INTERNAL>A/D CS C;SYS 27 A/D>>FOR<TECH 32'.A/D LICENS>>16'/0 OP REACT 15>>A/D>>RAD PROT 26'EP'IRr DHFS 29.DIRECTORS'EE 2'1<DIRECTORS'Lt 14 DIRECTOR,DST 30.EMRG PRP LIC I LEI 12!OR ASSESS BR 18 RAD'SMT'R EXTERNALS ACRS LPDR 03>>>>VT'I S" COPIES I>>TTR ENCL(7 7 16 16 1-1 1 1.RECIPIENT ID CODE/NAME'. | | ]'IZE: |
| 02'1 INPOrJ EST'ARNES NSIC 04 A/D CS S'NG 22'/D GEN PROJ 31 A/D MLQ ENG 23 A/D PLANT SYS25 A/D SAFETY AS17 D.IR'r EM=PREP 33 DIRECTOR'p DHF S2 8 DIRECTOR'g DSI 24 EMERG PREP DEV FKMA<<REP DIV OELD PDR EG F COPIKS LTTR>>ENCL<1 1=1 1 1 1 1 1 1 1 1.1>>l.1~1 1 1 1=0 1 1 f 1 1 1 ,-)ak'g~g gl TOTAL NUMBERS OF COPIES REQUIR ED j-" LiTTR 5 ENCL I"'~<<rtlj4~jW.~'" fbi<<I 0~I I I I lb'I 4~kjbC<<l',',I t'I~<<bI II<<I 41 l b<~It I W gb I~'I I"~'I I"I I<<14 I<<I I~I iW*~<<g~, I<<rt W'$4 N W i'I'1<<<<W q jtW ltt f'W C t<<1 Cq N C,t f I<<'I v p b II INDIANA L MICHIGAN ELECTRIC COMPANY P.O.BOX 18 BOWLING GREEN STATION NEW YORK, N.Y.10004 July 15, 1981 AEP:NRC:0584 Donald C.Cook Nuclear Plant Unit Nos.1 and 2 Docket Nos.50-315 and 50-316 License Nos.DPR-58 and DPR-74 NUREG-0737; ITEM II.B.1-REACTOR COOLANT SYSTEM VENTS Mr.Harold R.Denton, Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555
| | 'an Rgmts'OL's) |
| | TITLES= Response>> to NURKG <<0737 N TMI '~'NUREG<<0660 NOTESt-ILE'.3 copies" al 1 mat er el ~ 05000315 en copies of all matet'ial to ILK', 05000316" RECIPIENT COPIES RECIPIENT COPIKS ID>> CODE'/NAMEI I>>TTR ENCL( ID CODE/NAME'. LTTR>> ENCL< |
| | ACTION $ : ORB 0 f BC05>> 7 7 INTERNAL> A/D CS C; SYS 27 A/D CS S'NG 22'/D 1 1= |
| | A/D>> FOR< TECH 32'. GEN PROJ 31 1 1 A/D LICENS>> A/D MLQ ENG 23 1 1 A/D PLANT SYS25 16'/0 OP REACT 15>> |
| | DIRECTORS'EE 1 1 A/D>> RAD PROT A/D SAFETY AS17 1 DHFS 29.26'EP'IRr D.IR'r EM= PREP 33 1 2'1< DIRECTOR'p DHF S2 8 1. 1>> |
| | DIRECTORS'Lt 14 DIRECTOR'g DSI 24 l. 1 ~ |
| | DIRECTOR,DST 30. EMERG PREP DEV 1 1 EMRG PRP LIC FKMA<<REP DIV 1 1= |
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| | INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 July 15, 1981 AEP:NRC:0584 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG-0737; ITEM II.B.1 - REACTOR COOLANT SYSTEM VENTS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 |
| | |
| | ==Dear Mr. Denton:== |
| | |
| | This letter and its attachments document the engineering description, test procedures, background information, generic operating guidelines and supporting details for the reactor vessel head vents being installed in both Units of the Donald C. Cook Nuclear Plant. |
| | More specifically, the attachments to this letter contain the following information: |
| | Attachment 1: A brief description of the design, operation and testing requirements Attachment 2: Background Information for Pressurizer Venting Operation-Rev. 0, dated March 1981. |
| | s Attachment 3: Pressurizer Venting Operation - Rev. 0, dated March 1981. |
| | Attachment 4: Background Information for Reactor Head Vent Operation-Rev. 0,, dated February 1981. |
| | Attachment 5: Reactor Vessel Head Vent Operation - Rev. 0, dated February 1981. |
| | (/( |
| | 810721 0416 810715 PDR ADQCK 05000315 I P PDR |
| | |
| | -' |
| | T I V> |
| | J I I |
| | ) |
| | J' |
| | |
| | Mr.'arold R. Denton AEP:NRC:0584 : The following Supporting Information is attached: |
| | a) Suggested Technical Specifications. |
| | b) Flow Diagram of the Reactor Head Vent System (Figure 1). |
| | c) Flow Diagram of the Pressurizer Vent System (Figure 2). |
| | d) Logic Diagram (Figure 3). |
| | e) Elementary Wiring Diagram 6. |
| | Formal submittal of Technical, Specifications'will take place once, the sys-tem design is finalized. Westinghouse report WCAP-9600, "Report on Small Break Accidents for Westinghouse NSSS System", June 1979, Section 3.9 has been used as .a reference in developing the design of the vent system. |
| | This information is provided as requested in Item II.B.l of NUREG-0737. The Reactor Coolant System Venting Systems at the Cook Plant will be implemented by the required date of July 1, 1982. |
| | Very truly yours, |
| | . S. unter Vice President cc: John E. Dolan - Columbus R. C. Callen G. Charnoff R. W. Jurgensen D. V. Shaller - Bridgman Joe Williams, Jr. |
| | Region III Resident Inspector - Bridgman |
| | |
| | f I l |
| | 'I |
| | |
| | ATTACHMENT 1 TO AEP:NRC:05 Descr i tion of Desi n The reactor Coolant Vent System is comprised of the Reactor Head Vent System and the Pressurizer Vent System. It has been designed to vent a volume of Hydrogen approximately equal to one-half of the re-actor coolant system volume in one hour at system design pressure and temperature, Each of these subsystems consists of two parallel flow paths .'." |
| | one inch in size, with redundant isolation valves in each flow path. A 3/8" orifice has been installed upstream of the isolation valves to limit the flow in the case of a break downstream of the orifices to within the capacity of;-one centrifugal charging pump. A break of an RCS Vent Line upstream of,the orifices would result in a small LOCA not greater than .one inch in diameter. This type of break has been analyzed in WCAP-9600 (Reference 1) and would behave similarly to the hot leg break presented . |
| | in this report. Therefore a break in the vent line would not result in . |
| | a calculated core uncover . A locked open hand valve will be installed upstream of the 3/8" orifices. |
| | The isolation valves are D. C. powered, fail closed, solenoid valves with stem position switches. These valves can be operated from control .room.. They will be no@nally closed during plant operation. |
| | .'he Indicating 'hghts will be installed in the control room so the operators will know tne valve position. These valves will be qualified to IEEE-323-1974, IEEE-344-1975 an'd IEEE-383-1972. RTD assemblies have been added downstream of the solenoid valves to detect leakage through these valves.. |
| | These RTD "ssemblies will set off an alarm in the control room if leakage through the valves should occur. |
| | . The reactor vessel head vent connects to a part-length control rod drive mechanism housing located near the center of the reactor head. |
| | The pressurizer vent is connected to the pressurizer relief line. The possibility of reactor coolant pressure boundary leakage is minimized because of the two isolation valves in series. Isolation valves in one flow path are powered by Train A and the valves in the second flow path are powered by Train B. |
| | Both the reactor head vent and the pressurizer vent discharge into the upper volume of the .containment at approx. elevation 673'-0", |
| | in an area which will provide adequate dilution of any combustible gas. |
| | |
| | All piping and equipment used in the reactor head vent from the part-length rod housing to the orifices and all piping and equipment used in the pressurizer vent from the pressurizer relief piping to the orifices are designed in accordance with ASME, Section III Class 1 requirements. |
| | From the orifices up to the first anchor downstream of the second isolation valve the piping and equipment has been designed in accordance with ASME Section III Class 2 requirements. The remainder of the piping is designed to AEP Seismic Class 1 Level 4. |
| | ~Testin |
| | ~Otal The isolation valves used on the reactor head vent and pressurizer-vent will be tested in accordance with subsection IWV-3000 of ASME Section XI for Category B valves during refueling outages. |
| | P d The following procedures are attached and aregenerically applicable to the D. C. Cook Plant. |
| | : 1. Background Information for'Pressurizer Venting Operation - Rev. 0 dated March 1981. |
| | : 2. Pressurizer Venting Oper ation - Rev. 0 dated March 1981. |
| | : 3. Background Information for Reactor Head Vent Operation - Rev. 0 dated February 1981. |
| | : 4. Reactor Vessel Head Vent Operation - Rev. 0 dated February 1981. |
| | References |
| | : 1. WCAP-9600, "Report on Small Break Accidents for Westinghouse NSSS System," June 1979, (specifically Case. F Section 3.2). |
|
| |
|
| ==Dear Mr.Denton:==
| |
| This letter and its attachments document the engineering description, test procedures, background information, generic operating guidelines and supporting details for the reactor vessel head vents being installed in both Units of the Donald C.Cook Nuclear Plant.More specifically, the attachments to this letter contain the following information:
| |
| Attachment 1: A brief description of the design, operation and testing requirements Attachment 2: Attachment 3: Background Information for Pressurizer Venting Operation-Rev.0, dated March 1981.s Pressurizer Venting Operation-Rev.0, dated March 1981.Attachment 4: Background Information for Reactor Head Vent Operation-Rev.0,, dated February 1981.Attachment 5: Reactor Vessel Head Vent Operation-Rev.0, dated February 1981.810721 0416 810715 I PDR ADQCK 05000315 P PDR (/(
| |
| -'T I J V>I I)J' Mr.'arold R.Denton AEP:NRC:0584 Attachment 6: The following Supporting Information is attached: a)Suggested Technical Specifications.
| |
| b)Flow Diagram of the Reactor Head Vent System (Figure 1).c)d)Flow Diagram of the Pressurizer Vent System (Figure 2).Logic Diagram (Figure 3).e)Elementary Wiring Diagram 6.Formal submittal of Technical, Specifications'will take place once, the sys-tem design is finalized.
| |
| Westinghouse report WCAP-9600,"Report on Small Break Accidents for Westinghouse NSSS System", June 1979, Section 3.9 has been used as.a reference in developing the design of the vent system.This information is provided as requested in Item II.B.l of NUREG-0737.The Reactor Coolant System Venting Systems at the Cook Plant will be implemented by the required date of July 1, 1982.Very truly yours,.S.unter Vice President cc: John E.Dolan-Columbus R.C.Callen G.Charnoff R.W.Jurgensen D.V.Shaller-Bridgman Joe Williams, Jr.Region III Resident Inspector-Bridgman f I l'I ATTACHMENT 1 TO AEP:NRC:05 Descr i tion of Desi n The reactor Coolant Vent System is comprised of the Reactor Head Vent System and the Pressurizer Vent System.It has been designed to vent a volume of Hydrogen approximately equal to one-half of the re-actor coolant system volume in one hour at system design pressure and temperature, Each of these subsystems consists of two parallel flow paths.'." one inch in size, with redundant isolation valves in each flow path.A 3/8" orifice has been installed upstream of the isolation valves to limit the flow in the case of a break downstream of the orifices to within the capacity of;-one centrifugal charging pump.A break of an RCS Vent Line upstream of, the orifices would result in a small LOCA not greater than.one inch in diameter.This type of break has been analyzed in WCAP-9600 (Reference 1)and would behave similarly to the hot leg break presented.in this report.Therefore a break in the vent line would not result in.a calculated core uncover.A locked open hand valve will be installed upstream of the 3/8" orifices.The isolation valves are D.C.powered, fail closed, solenoid valves with stem position switches.These valves can be operated from.'he control.room..They will be no@nally closed during plant operation.
| |
| Indicating
| |
| 'hghts will be installed in the control room so the operators will know tne valve position.These valves will be qualified to IEEE-323-1974, IEEE-344-1975 an'd IEEE-383-1972.
| |
| RTD assemblies have been added downstream of the solenoid valves to detect leakage through these valves..These RTD"ssemblies will set off an alarm in the control room if leakage through the valves should occur..The reactor vessel head vent connects to a part-length control rod drive mechanism housing located near the center of the reactor head.The pressurizer vent is connected to the pressurizer relief line.The possibility of reactor coolant pressure boundary leakage is minimized because of the two isolation valves in series.Isolation valves in one flow path are powered by Train A and the valves in the second flow path are powered by Train B.Both the reactor head vent and the pressurizer vent discharge into the upper volume of the.containment at approx.elevation 673'-0", in an area which will provide adequate dilution of any combustible gas. All piping and equipment used in the reactor head vent from the part-length rod housing to the orifices and all piping and equipment used in the pressurizer vent from the pressurizer relief piping to the orifices are designed in accordance with ASME, Section III Class 1 requirements.
| |
| From the orifices up to the first anchor downstream of the second isolation valve the piping and equipment has been designed in accordance with ASME Section III Class 2 requirements.
| |
| The remainder of the piping is designed to AEP Seismic Class 1 Level 4.~Testin The isolation valves used on the reactor head vent and pressurizer-vent will be tested in accordance with subsection IWV-3000 of ASME Section XI for Category B valves during refueling outages.~Otal P d The following procedures are attached and aregenerically applicable to the D.C.Cook Plant.1.Background Information for'Pressurizer Venting Operation-Rev.0 dated March 1981.2.Pressurizer Venting Oper ation-Rev.0 dated March 1981.3.Background Information for Reactor Head Vent Operation-Rev.0 dated February 1981.4.Reactor Vessel Head Vent Operation-Rev.0 dated February 1981.References 1.WCAP-9600,"Report on Small Break Accidents for Westinghouse NSSS System," June 1979, (specifically Case.F Section 3.2).
| |
| ATTACHMENT E T0 AEP:NRC:0584}} | | ATTACHMENT E T0 AEP:NRC:0584}} |
Forwards Info Re Engineering Description,Test Procedures, Background Info,Generic Operating Guidelines & Supporting Details for Reactor Vessel Head Vents,In Response to NUREG- 0737,Item II.B.1| ML17331A772 |
| Person / Time |
|---|
| Site: |
Cook  |
|---|
| Issue date: |
07/15/1981 |
|---|
| From: |
Hunter R
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
|---|
| To: |
Harold Denton
Office of Nuclear Reactor Regulation |
|---|
| Shared Package |
|---|
| ML17319A959 |
List: |
|---|
| References |
|---|
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-TM AEP:NRC:0584, AEP:NRC:584, NUDOCS 8107210416 |
| Download: ML17331A772 (9) |
|
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Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
ML17325B4641999-03-17017 March 1999
Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation
1999-09-30
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17328A4481990-09-21021 September 1990
Requests Withdrawal of Mode 6 Proposed Tech Spec Change Since Issue Currently Being Addressed by New STSs
ML17328A4331990-08-27027 August 1990
Informs of Preliminary Assessment of 900713 Electrical Contact Accident at Facility.Investigation Concludes That No Safety Rules Violated
ML17328A4001990-08-24024 August 1990
Responds to 900725 Ltr Re Commitments Made in Response to Generic Ltr 88-14 on Instrument Air Supply Problems Affecting safety-related Equipment.Simulator Training to Be Provided as Stated
ML17334B3781990-08-24024 August 1990
Forwards Info to Certify Plant Simulator Facility.Results of Evaluation of Dual Unit Simulation Facilities Demonstrate That Plant Simulator Performance Compares Favorably W/Units
ML17328A4231990-08-21021 August 1990
Forwards Under Separate Cover,Semiannual Radioactive Effluent Release Rept for Jan-June 1990
ML17328A3901990-08-17017 August 1990
Responds to NRC 900720 Ltr Re Violations Noted in Onsite Audit of Spds.Corrective Actions:Apparent Disparity in Selection of Reactor Trip & Sys Capacity or Anticipatory Values Rectified
ML17328A3891990-08-15015 August 1990
Forwards Performance Data Sheets for Plant fitness-for-duty Program for Period Jan-June 1990,per 10CFR26.Encl Includes Statistics on Various Categories of Testing,Substances Tested for & cut-off Levels Used
ML17328A3571990-08-0202 August 1990
Responds to Open Items in Safety Evaluation of Util Response to Unresolved Issues on post-fire Safe Shutdown Methodology. Open Items 1 & 21 Will Be Closed by Implementing Plant Procedures Providing Equivalent Degree of Protection
ML17328A3431990-07-23023 July 1990
Requests Withdrawal of 890830 Proposed Tech Spec Changes Re Sections 3.0 & 4.0.Util Will Resubmit Generic Ltr 87-09 Recommended Improvement Items on Case by Case Basis
ML17328A3421990-07-23023 July 1990
Provides Results of Offsite Dose Calculation for Reactor Coolant Pump Locked Rotor Event for Facility Cycle 8.Util Identified Previously Issued SERs Addressing Short Term Containment Analysis & LOCA Containment Integrity
ML20055G7551990-07-18018 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-315/90-10 & 50-316/90-10.Corrective Actions:Required Review Performed & Updated Procedure 12 Mhp 5021.019.001 Revised & Issued
ML17328A3191990-07-12012 July 1990
Responds to NRC 900601 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Electrical Testing Techniques Improved & Surveillance Procedures for Feedwater Pumps Will Be Rewritten
ML17328A3181990-07-0909 July 1990
Responds to Generic Ltr 90-03,Suppl 1, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2,Part 2, 'Vendor Interface for Safety-Related Components.' Licensee Will Contact safety-related Vendors on Annual Basis
ML17328A3111990-07-0303 July 1990
Provides Certification of Funding Plan for Decommissioning of Plant,Per 10CFR50.33 & 50.75
ML17328A2961990-06-25025 June 1990
Forwards Response to Generic Ltr 90-04 Re Closeout of Generic Safety Issues.Util Supports Concern & Desire to Close long-standing Generic Safety Issues
ML17328A2921990-06-22022 June 1990
Forwards WCAP-12483, Analysis of Capsule U from American Electric Power Co DC Cook Unit 1 Reactor Vessel Radiation Surveillance Program.
ML20044A3521990-06-22022 June 1990
Submits Info Re Sensitivity Study Performed on Number of Fuel Axial Intervals,Per Topical Rept, American Electric Power Reactor Core Thermal-Hydraulic Analysis Using Cobra III-C/MIT-2 Computer Code.
ML17328A2821990-06-15015 June 1990
Submits Ltr Re Proposed Control Room Habitability Tech Spec Changes & Supporting Analyses,Per 900521 Discussion.Revised Calculations of Control Room Thyroid Doses Will Be Submitted within 60 Days of Receipt of Proposed Generic Ltr
ML17328A2741990-06-12012 June 1990
Submits Followup,Per 900205 & 0308 Ltrs & Provides Update Re Inoperable Fire Barrier.Fire Seal Repaired & Restored to Operability on 900419
ML17328A2551990-06-0505 June 1990
Forwards Addl Info Re Util 900126 Revised Response to NRC Bulletin 88-002,per NRC 900509 Request
ML17328A7361990-06-0101 June 1990
Forwards Addl Info Re 890825 & 1212 Applications for Amends to Licenses DPR-58 & DPR-74,per Request.Amends Make Changes to Administrative Controls
ML17328A7331990-05-29029 May 1990
Forwards Nonproprietary WCAP-12577 & Proprietary WCAP-12576, Westinghouse Revised Thermal Design Procedure Instrument... Methodology for American Electric Power DC Cook Unit 2 Nuclear Power Station, Per 900419 Commitment
ML17328A7321990-05-24024 May 1990
Responds to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount. No Rosemount Model 1153 Series B or D or Model 1154 Transmitters Installed at Facility.Transmitters Purchased as commercial-grade Units
ML17328A6991990-05-0909 May 1990
Provides Suppl to 900103 Response,Certifying That Fitness for Duty Program Implemented at Plant.Change Also Clarifies When More Stringent cut-off Levels Adopted at Plant Program Apply
ML17328A7001990-05-0909 May 1990
Responds to NRC 900406 Ltr Re Inadequacies of Spds,Per Audit on 900221-22.Corrective Actions:Software Mod Will Prevent User from Accessing Displays Other than Iconic Displays from SPDS Dedicated Terminal
ML17328A7071990-05-0707 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept Mar 1990 for Donald C Cook Nuclear Plant Unit 1
ML17328A7031990-05-0707 May 1990
Forwards Monthly Operating Rept for Apr 1990 & Corrected Rept for Mar 1990 for DC Cook Nuclear Plant Unit 2
ML17328A6951990-04-30030 April 1990
Certifies That Training Programs for Initial Licensing & Requalification Training of Operators & Senior Operators at Plant Accredited by Inpo,Per Generic Ltr 87-07
ML17328A6861990-04-30030 April 1990
Forwards Annual Environ Operating Rept,Jan-Dec 1989, & DC Cook Nuclear Plant Units 1 & 2 Operational Radiological Environ Monitoring Program 1989 Rept Jan-Dec 1989.
ML17328A6801990-04-23023 April 1990
Responds to NRC Bulletin 88-004, Potential Safety-Related Pump Loss. Study Planned to Evaluate Alternative Actions to Be Taken for Protecting RHR Pumps
ML17328A6771990-04-23023 April 1990
Forwards DC Cook Nuclear Plant 1990 Annual Emergency Preparedness Exercise. Exercise Scope & Objectives & Detailed Scenario Documentation Encl
ML17334B3641990-04-11011 April 1990
Responds to NRC 900301 Ltr Re Violations Noted in Insp Repts 50-315/89-31 & 50-316/89-31.Corrective Actions:Reliability Centered Maint Program Initiated
ML17328A6601990-04-11011 April 1990
Forwards Updated QA Program Description for Cook Nuclear Plant, Incorporating Editorial,Organizational & Position Title Changes
ML17328A6551990-04-0909 April 1990
Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-316/90-08.Corrective Actions:Procedure for Steam Generator Stop Valve Operability Test Revised to Require That MSIV Be Declared Inoperable After Failing Stroke Test
ML17334B3601990-04-0606 April 1990
Forwards Revised Figures for Loss of Load Event Previously Submitted in Attachment 4,App B of Vantage 5 Reload Transition Safety Rept Supplied by Westinghouse in Jan 1990. Update Is Editorial in Nature
ML17334B3621990-04-0606 April 1990
Forwards 1989 Annual Rept & Projected Cash Flow
ML17328A6341990-03-30030 March 1990
Forwards Application for Renewal of Plant NPDES Permit,For Info,Per Section 3.2 of App B to Plant Tech Specs.W/O Encl
ML17328A6331990-03-30030 March 1990
Responds to NUMARC 900104 Request for Addl Info Re Station Blackout Submittals.Target Reliability for Emergency Diesel Generator of 0.0975 Established for 4 H ac-independent Coping Category Will Be Maintained
ML17328A6321990-03-30030 March 1990
Forwards Response to Generic Ltr 90-01, NRC Regulatory Impact Survey. Util Ack Recommendation by NUMARC
ML17328A6221990-03-27027 March 1990
Responds to 900226 Ltr Transmitting Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000. Corrective Actions:Flow Retention Circuitry Setpoints Set to Compensate for Missized Process Flow Orifice
ML17328A6191990-03-27027 March 1990
Forwards Payment in Amount of $75,000 for Civil Penalty Imposed Through Notice of Violation Issued in Insp Rept 50-316/89-02 on 891016-20,24-26 & 1204.Response to Violation & Corrective Actions Provided in Separate Submittal
ML17328A6161990-03-20020 March 1990
Responds to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs (USI A-47).Both Units Have Steam Overfill Protection Sys That Would Automatically Prevent Water Carryover Into Steam Lines If Control Sys Failed
ML17328A6121990-03-13013 March 1990
Forwards Monthly Performance Monitoring Rept,Jan 1990.
ML17325B3901990-03-0606 March 1990
Forwards Annual Rept to NRC Per 10CFR50.54(W)(2) Re Nuclear Property Insurance
ML17325B3921990-03-0606 March 1990
Modifies Application for Amend to License DPR-74 Re Cycle 8, Per 900228 Telcon
ML17325B3781990-02-28028 February 1990
Forwards Response to NRC Info Notice 89-056 Re Questionable Certification of Matl Supplied to Dod by Nuclear Suppliers. Matl Capable of Performing Design Function & Acceptable for Continued Use
ML17328A5971990-02-27027 February 1990
Withdraws 890203 Application for Amend to License DPR-74, Modifying Tech Spec Table 3.2-1 Re DNB Parameters to Express RCS Flow Rate on Volumetric Rather than Mass Basis
ML17334B3511990-02-22022 February 1990
Submits Annual Rept of Changes to or Errors in Acceptable LOCA Evaluation Models or Application of Models for Plants. Wflash Analyses Will Be Superceded by Notrump Analyses for Unit 2,Cycle 8 Reload
ML17328A5881990-02-21021 February 1990
Responds to NRC 890914 Request for Addl Info Re Safe Shutdown Methodology.App R Fire Barriers Being Maintained & Surveilled Under 3/4.7.10 for Units 1 & 2
ML17328A5861990-02-16016 February 1990
Provides Revised Comments in Response to NRR Comments During 891213 Telcon Re Allowable Stresses for Piping & Piping Supports
1990-09-21
[Table view] |
Text
REGULATORY NFORMATION DISTRIBUTION SY TEM (R IDS)
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INDIANA L MICHIGAN ELECTRIC COMPANY P. O. BOX 18 BOWLING GREEN STATION NEW YORK, N. Y. 10004 July 15, 1981 AEP:NRC:0584 Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 NUREG-0737; ITEM II.B.1 - REACTOR COOLANT SYSTEM VENTS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Denton:
This letter and its attachments document the engineering description, test procedures, background information, generic operating guidelines and supporting details for the reactor vessel head vents being installed in both Units of the Donald C. Cook Nuclear Plant.
More specifically, the attachments to this letter contain the following information:
Attachment 1: A brief description of the design, operation and testing requirements Attachment 2: Background Information for Pressurizer Venting Operation-Rev. 0, dated March 1981.
s Attachment 3: Pressurizer Venting Operation - Rev. 0, dated March 1981.
Attachment 4: Background Information for Reactor Head Vent Operation-Rev. 0,, dated February 1981.
Attachment 5: Reactor Vessel Head Vent Operation - Rev. 0, dated February 1981.
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Mr.'arold R. Denton AEP:NRC:0584 : The following Supporting Information is attached:
a) Suggested Technical Specifications.
b) Flow Diagram of the Reactor Head Vent System (Figure 1).
c) Flow Diagram of the Pressurizer Vent System (Figure 2).
d) Logic Diagram (Figure 3).
e) Elementary Wiring Diagram 6.
Formal submittal of Technical, Specifications'will take place once, the sys-tem design is finalized. Westinghouse report WCAP-9600, "Report on Small Break Accidents for Westinghouse NSSS System", June 1979, Section 3.9 has been used as .a reference in developing the design of the vent system.
This information is provided as requested in Item II.B.l of NUREG-0737. The Reactor Coolant System Venting Systems at the Cook Plant will be implemented by the required date of July 1, 1982.
Very truly yours,
. S. unter Vice President cc: John E. Dolan - Columbus R. C. Callen G. Charnoff R. W. Jurgensen D. V. Shaller - Bridgman Joe Williams, Jr.
Region III Resident Inspector - Bridgman
f I l
'I
ATTACHMENT 1 TO AEP:NRC:05 Descr i tion of Desi n The reactor Coolant Vent System is comprised of the Reactor Head Vent System and the Pressurizer Vent System. It has been designed to vent a volume of Hydrogen approximately equal to one-half of the re-actor coolant system volume in one hour at system design pressure and temperature, Each of these subsystems consists of two parallel flow paths .'."
one inch in size, with redundant isolation valves in each flow path. A 3/8" orifice has been installed upstream of the isolation valves to limit the flow in the case of a break downstream of the orifices to within the capacity of;-one centrifugal charging pump. A break of an RCS Vent Line upstream of,the orifices would result in a small LOCA not greater than .one inch in diameter. This type of break has been analyzed in WCAP-9600 (Reference 1) and would behave similarly to the hot leg break presented .
in this report. Therefore a break in the vent line would not result in .
a calculated core uncover . A locked open hand valve will be installed upstream of the 3/8" orifices.
The isolation valves are D. C. powered, fail closed, solenoid valves with stem position switches. These valves can be operated from control .room.. They will be no@nally closed during plant operation.
.'he Indicating 'hghts will be installed in the control room so the operators will know tne valve position. These valves will be qualified to IEEE-323-1974, IEEE-344-1975 an'd IEEE-383-1972. RTD assemblies have been added downstream of the solenoid valves to detect leakage through these valves..
These RTD "ssemblies will set off an alarm in the control room if leakage through the valves should occur.
. The reactor vessel head vent connects to a part-length control rod drive mechanism housing located near the center of the reactor head.
The pressurizer vent is connected to the pressurizer relief line. The possibility of reactor coolant pressure boundary leakage is minimized because of the two isolation valves in series. Isolation valves in one flow path are powered by Train A and the valves in the second flow path are powered by Train B.
Both the reactor head vent and the pressurizer vent discharge into the upper volume of the .containment at approx. elevation 673'-0",
in an area which will provide adequate dilution of any combustible gas.
All piping and equipment used in the reactor head vent from the part-length rod housing to the orifices and all piping and equipment used in the pressurizer vent from the pressurizer relief piping to the orifices are designed in accordance with ASME,Section III Class 1 requirements.
From the orifices up to the first anchor downstream of the second isolation valve the piping and equipment has been designed in accordance with ASME Section III Class 2 requirements. The remainder of the piping is designed to AEP Seismic Class 1 Level 4.
~Testin
~Otal The isolation valves used on the reactor head vent and pressurizer-vent will be tested in accordance with subsection IWV-3000 of ASME Section XI for Category B valves during refueling outages.
P d The following procedures are attached and aregenerically applicable to the D. C. Cook Plant.
- 1. Background Information for'Pressurizer Venting Operation - Rev. 0 dated March 1981.
- 2. Pressurizer Venting Oper ation - Rev. 0 dated March 1981.
- 3. Background Information for Reactor Head Vent Operation - Rev. 0 dated February 1981.
- 4. Reactor Vessel Head Vent Operation - Rev. 0 dated February 1981.
References
- 1. WCAP-9600, "Report on Small Break Accidents for Westinghouse NSSS System," June 1979, (specifically Case. F Section 3.2).
ATTACHMENT E T0 AEP:NRC:0584