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| {{#Wiki_filter:tt llEulllll IHiZ ANO zzgw zw'Im'uit ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y.I4649 JOHN E.MA IER VICE PRESIDENT TCL,EPHONE ARCA cOOK Tld 546-2700 September 25, 1981 Director of Nuclear Reactor Regulation Attention: | | {{#Wiki_filter:tt llEulllll IHiZ ANO zzgw zw |
| Mr.Dennis M.Crutchf ield, Chief Operating Reactors Branch 55 U.S.Nuclear Regulatory Commission Washington, D.C.20555 | | 'Im'uit ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. I4649 JOHN E. MA IER TCL,EPHONE VICE PRESIDENT ARCA cOOK Tld 546-2700 September 25, 1981 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchf ield, Chief Operating Reactors Branch 55 gag '-g); |
| | U. S. Nuclear Regulatory Commission Washington, D.C. 20555 1981~ 12 graf Ij~g~ Nlgj |
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| ==Subject:== | | ==Subject:== |
| SEP Topics VI-7.A.3 and VI-10.A R.E.Ginna Nuclear Power Plant Docket No.50-244<gag'-g);1981~12 graf I j~g~Nlgj | | SEP Topics VI-7.A.3 and VI-10.A R. E. Ginna Nuclear Power Plant Docket No. 50-244 |
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| ==Dear Mr.Crutchfield:== | | ==Dear Mr. Crutchfield:== |
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| This letter is in response to your letter of December 15, 1980, transmitting the final SEP assessments for these two topics to Rochester Gas and Electric.Four items requiring resolution during the Integrated Assessment for Ginna were identified in these assessments. | | This letter is in response to your letter of December 15, 1980, transmitting the final SEP assessments for these two topics to Rochester Gas and Electric. Four items requiring resolution during the Integrated Assessment for Ginna were identified in these assessments. The information in the enclosure should resolve these concerns prior to the Integrated Assessment. |
| The information in the enclosure should resolve these concerns prior to the Integrated Assessment. | | Very truly yours, hn E. Maier Enclosure |
| Very truly yours, hn E.Maier Enclosure',Sii0020253 8i0925 ,'PDR ADOCK 05000244 P PDR t g 4W i'4l I-j'I h~(q~a li | | ',Sii0020253 8i0925 |
| | ,'PDR ADOCK 05000244 P PDR |
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| | t g I-i '4l4W j'I |
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| | ~ ( q a li |
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| ==Enclosure:== | | ==Enclosure:== |
| | RG&E Responses to Concerns Identified in the Evaluation and Conclusions of the SEP Assessment for SEP Topics VI-7.A.3 and VI-10.A, 12/15/80 |
| | : 1. The instrumentation strings from sensors thru bistable devices are not response time tested. As a result, the testing required by IEEE Std. 279-1968 Section 4.10 is not satisfied because the response time design basis (IEEE 279-1968 Section 3 (i)) is not verified. |
| | Response: RG&E does not, at this time perform response time testing of instrumentation strings for the Engineered Safety Feature System. We disagree, however, that the lack of such testing violates the provisions of IEEE 279-1968. |
| | RG&E does perform testing to verify that the final actuated devices are properly operational within the times assumed in the plant design basis. Appropriate test procedures were sent to the NRC with RG&E's trans-mittal of September 10, 1980. |
| | The Ginna design does not conform with the provisions of Regulatory Guide 1.118, "Periodic Testing of Electric Power and Protection Systems." This regulatory guide was published long after Ginna became operational; it was thus obviously not considered in the design of the plant. The latest version of Regulatory Guide 1.118 (Rev. 2 published June 1978), states that this regulatory guide ". . . is'being and will continue to be used in the evaluation of submittals in connection with Construction Permit a lications . . ." (emphasis added). The implementation of this regulatory guide does not provide specific provisions for backfitting; it is not directly applicable to Ginna. RG&E further does not believe that strict adherence to the guidance provided in Regulatory Guide 1.118 is necessary to meet IEEE-279-1968 requirements. RG&E performs periodic tests and calibration on all components of the protection system instrumentation strings, including sensors. Any significant degradation in component response will be identified and corrected by this activity. RG&E is also preparing to implement certain response time testing at the Ginna plant. Ginna Technical Specifi-cations 4.4.6.2 and 4.8.10 require that the response time of each containment isolation function and each auxiliary feedwater initiation function be demonstrated to be within required limits at least once per 18 months. RG&E is presently developing a program to effect this requirement. |
| | It is considered that the current methodology meets the requirements of this SEP topic. This issue does not need to be considered further within the Systematic Evaluation Program. |
| | |
| | 1 M |
| | : 2. The test procedures required the removal of fuses and installation of jumpers to block equipment operation and/or to simulate contact closure. The procedures often do not specify the time at which these jury-rigged modifications are removed. This situation is a violation of IEEE,Std. |
| | 279-1968 Sections 4.13 and 4.20. |
| | Response: RGGE is unclear as to how this conclusion was drawn from a review of the Ginna test procedures. When the removal of fuses and installation of jumpers to block equipment operation and'/or 'simulate contact closure is required as part of a test procedure, the alignment of this equipment to its original configuration is also specified in the procedure. |
| | If the use of jumper control is needed, when is not directly specified in an approved maintenance, cali-it bration, test, or modification procedure, procedure A-1402, "Bypass of Safety Function or Jumper Control" is used. Installation and removal of any such jumpers is performed by two knowledgeable individuals, one being the job foreman. A copy of this procedure, Rev. |
| | 1, is attached. |
| | RG&E thus considers the procedures for use of jumpers and fuses acceptable, and in conformance with IEEE 279-1968. |
| | The test procedures require that certain equipment be removed from service by racking out breakers and by pull to stop switches as well as the use of jumpers and removal of fuses discussed above. These test methods violate Section 4.20 of IEEE Std. 279-1968 because they are not annunciated to the operator in a timely manner such as to provide him with an unambiguous indication of the status of equipment needed to protect the public health and safety. |
| | Response: RGGE requires that, any safety system which is temporarily rendered inoperable due to testing during normal plant operations be monitored by the Ginna "Test Tag Control Program" (Procedure A-1103). A copy of this procedure is included. In addition, any testing, maintenance, or other operation performed on a safety-related piece of equipment at Ginna must be approved by the shift super-visor. Information about the operability of safety-related equipment to control room personnel is thus further assured. I I 1 |
| | I I f4 ~,( |
| | : 4. As noted in Topic VI-4 we have also discovered |
| | ~ |
| | that the . |
| | override of an automati.c ESF actuation signal incapacitates the system level manual actuation features. |
| | Response: This concern was addressed in letters from John E. Maier (RGEE) to Dennis M. Crutchfield (NRC) dated March 2, 1981 and September 18, 1981. Resolution of any ad-ditional items is being addressed under SEP Topic VI-4. |
| | 2 |
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| | 0 g)NqP, 87/~7loh UHli <<1 COMPL" TED ROCHESTER GAS AND ELECTRIC CORPORATION DATE:- |
| | GINNA STATION T)MF.:- |
| | CONTROLLED COPY NUMBER PROCEDURE NO. A-1402 'REV. NO ~ |
| | BYPASS OF SAFETY FUNCTION OR JUMPER CONTROL TECHNICAL REVIEW PORC 4/8/81 Q. A. REVIEW QC REVIEW 0 /2 6 II i'i-- DATE APPROVED FOR USE LANT SUPERIiNTENDENT DATE QA- NON-QA CATAGORY 1.0 REVIEWED BY |
| | 'HIS PROCEDURE COiNTAINS 3 PAGES |
| | |
| | j |
| | ~, ~ ~ |
| | A-1402:1 A-1402 BYPASS OF SAFETY FUNCTION OR JUMPER CONTROL |
| | |
| | ==1.0 PURPOSE== |
| | To control the use of jumper. wires, lifted wire, pulled fuses, use of states blocks, spool pieces, -blank flanges, or other means to bypass, defeat or permit a device to perform or not perform its intended function. |
| | 1.2 This procedure does not apply when the functon is altered as part of an approved maintenance, calibration, test or modification procedure, nor does it apply to use of installed switches or buttons. |
| | |
| | ==2.0 REFERENCES== |
| | 2.1 None |
| | |
| | ==3.0 INSTRUCTIONS== |
| | 3.1 The multileaf request form should normally be initiated by the Job Foreman by signature on the request form. |
| | 3.1. 1 Two knowledgeable individuals, one being the job foreman, shall concur on the location and clearly describe. Terminal point locations, wire number, fuse number, or other description shall be used. |
| | 3.1.2 The Job Foreman shall ensure the function and purpose are listed. |
| | 3.2 The Shift Supervisor or alternate shall review the request for safety significance and effects on plant operations to determine whether the request should be approved or disapproved. |
| | 3.3 If approved, the Shift Supervisor or alternate shall assign a sequential Request Ik, preceded by the year (i.e., 80-1). |
| | Implementation shall be verified by two knowledgeable individuals. |
| | I 3.4.1 Identification tags shall be attached to the jumper wire, lifted wire, or other device, as appropriate, to clearly identify the device. |
| | NOTE: If it is not feasible to physically attach the tag to the device, the tag should be fastened in the immediate area. |
| | 3.4.2 |
| | ~ ~ Removal shall be verified by two knowledgeable individuals; |
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| | ( ~ ~ |
| | ~ |
| | ~ |
| | A-1402:2 The Official Record shall indicate when this is performed, and when it is removed. |
| | 3.6 The Shift Supervisor shall review the active binder before a unit startup to ensure plant requirements are met. |
| | |
| | ==4.0 RECORDS== |
| | 4.1 The multileaf request form original shall remain in the Shift Super-visor's active binder until completed, and then submitted to Central Records. |
| | L 4.2 The yellow copy shall go to the Job Foreman, and may be destroyed when completed. |
| | 4.3 Jumper control tag(s) may be destroyed when completed. |
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| | ~ ~ |
| | E ~ ~ ~ ' A->402:3 |
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| | ROCHESTER GAS AND ELECTRIC RMCRCTTCK PROCCOURC Al&R GINNA STATION BYPASS OF SAFETY FUNCTION AND JUMPER CONTROL T |
| | JOB FOREMAHT OATEE REQUEST A VERIFIED BYT JUMPER WIRE Q LIFTED WIRE Q FUSES PULLED Q STATES BLOCK Q OTHER Q FUNCTION PURPOSE LOCATIONI SHIFT SUPERYISORT DATE> |
| | ~IHSTLLL TIOII EE~Y DATE 4 TIME DATE 8 TIME ENTERED IH OfFICIAL LOG; KHTERED IH OFFICIAI. LOG; NUMBER OF TAGS ISSUED: NUMBER OF TAG REMOVED: |
| | INSTALLED BYT REMOVEO BYT YERIF IED BYT VERIFIED BYT |
| | ~ I T42 A |
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| | 0 C ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO. A-1103 REV. NO. |
| | TEST TAG CONTROL PROGRAM TECHNICAL REVIEW PORC 3/4/81 QC REVIEW DATE APPROVED FOR USE LANT SUPERINTENDENT DATE QA X NON-QA CATAGORY 1.0 REVIEWED BY'HIS PROCEDURE CONTAINS 5 PAGES |
| | |
| | A-1103:1 A-1103 TEST TAG CONTROL PROGRAM 1.0 PURPOSE:, |
| | This procedure describes the test control program for surveillance testing and fo'r "special tests on equipment, systems, and structures under the jurisdiction of the Shift Supervisor. |
| | 1.2 This procedure'lso provides'a'method for indicating the status of a Nuclear Safety System which is temporarily inoperable because of testing during normal plant operations. |
| | |
| | ==2.0 REFERENCES== |
| | 'inna 2.1 Quality Assurance Manual, Section 14. |
| | 2.2 Regulatory Guide 1.47 "Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety System". |
| | 3.0 INSTRUCTIONS'.1 Description 3;1.1 A test control program utilizing test tags (See Figure 1) and a test control log (See Figure 2), shall be utilized to provide the status indication and control of systems and equipment involved in the various tests. Valves, switches and other devices included in the test control program shall include: |
| | 3.1.1.1 Those major components positioned out of their normal position for the duration of'he test. |
| | 3.1.1.2 Those boundary valves which are desired to remain closed during the test. |
| | 3.1.1.3 Throttling valves under the control of test personnel. |
| | 3.1.1.4 Critical system valves to remain open during the test. |
| | 3.1.1.5 Valves placed out-of-normal alignment during verification of interlock functions need not be tagged if returned to normal position in a minimal amount of time. |
| | NOTE: This s stem is not to be confused or used in lace of the regular "Hold" s stem which is for the rotection of e ui ment and personnel. |
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| RG&E Responses to Concerns Identified in the Evaluation and Conclusions of the SEP Assessment for SEP Topics VI-7.A.3 and VI-10.A, 12/15/80 1.The instrumentation strings from sensors thru bistable devices are not response time tested.As a result, the testing required by IEEE Std.279-1968 Section 4.10 is not satisfied because the response time design basis (IEEE 279-1968 Section 3 (i))is not verified.Response: RG&E does not, at this time perform response time testing of instrumentation strings for the Engineered Safety Feature System.We disagree, however, that the lack of such testing violates the provisions of IEEE 279-1968.RG&E does perform testing to verify that the final actuated devices are properly operational within the times assumed in the plant design basis.Appropriate test procedures were sent to the NRC with RG&E's trans-mittal of September 10, 1980.The Ginna design does not conform with the provisions of Regulatory Guide 1.118,"Periodic Testing of Electric Power and Protection Systems." This regulatory guide was published long after Ginna became operational; it was thus obviously not considered in the design of the plant.The latest version of Regulatory Guide 1.118 (Rev.2 published June 1978), states that this regulatory guide"...is'being and will continue to be used in the evaluation of submittals in connection with Construction Permit a lications..." (emphasis added).The implementation of this regulatory guide does not provide specific provisions for backfitting; it is not directly applicable to Ginna.RG&E further does not believe that strict adherence to the guidance provided in Regulatory Guide 1.118 is necessary to meet IEEE-279-1968 requirements.
| | A-1103:2 |
| RG&E performs periodic tests and calibration on all components of the protection system instrumentation strings, including sensors.Any significant degradation in component response will be identified and corrected by this activity.RG&E is also preparing to implement certain response time testing at the Ginna plant.Ginna Technical Specifi-cations 4.4.6.2 and 4.8.10 require that the response time of each containment isolation function and each auxiliary feedwater initiation function be demonstrated to be within required limits at least once per 18 months.RG&E is presently developing a program to effect this requirement.
| | : 3. 1.2 The. "SAFE GUARDS TRAIN MODE INACTIVE" This section of the TEST CONTROL LOG SHEET shall be used to indicate any nuclear safety systems made inoperable for more than 1 hour as a result of the related equipment involved in a test. |
| It is considered that the current methodology meets the requirements of this SEP topic.This issue does not need to be considered further within the Systematic Evaluation Program.
| | 3.2 Tag Control Procedure 3.2.1 Prior to the start of the test, the test coordinator (Qualified Test Personnel Level II or III) shall review the Test Procedure with the "STATION HOLDING AUTHORITY" for test tag requirements after receiving permission to perform the test. |
| 1 M 2.The test procedures required the removal of fuses and installation of jumpers to block equipment operation and/or to simulate contact closure.The procedures often do not specify the time at which these jury-rigged modifications are removed.This situation is a violation of IEEE,Std.279-1968 Sections 4.13 and 4.20.Response: RGGE is unclear as to how this conclusion was drawn from a review of the Ginna test procedures.
| | 3.2.2 All test tags shall be logged in the Test Control Log by the Test Coordinator with each entry to include the following information: |
| When the removal of fuses and installation of jumpers to block equipment operation and'/or'simulate contact closure is required as part of a test procedure, the alignment of this equipment to its original configuration is also specified in the procedure.
| | EQUIPMENT; POSITION DURING TEST; TEST NUMBER; TEST COORDINATOR; PERFORMED BY; DATE AND DATE TEST PERFORMED; SAFEGUARDS TRAIN MODE INACTIVE (AS APPLICABLE) AND STATION HOLDING AUTHORITY. |
| If the use of jumper control is needed, when it is not directly specified in an approved maintenance, cali-bration, test, or modification procedure, procedure A-1402,"Bypass of Safety Function or Jumper Control" is used.Installation and removal of any such jumpers is performed by two knowledgeable individuals, one being the job foreman.A copy of this procedure, Rev.1, is attached.RG&E thus considers the procedures for use of jumpers and fuses acceptable, and in conformance with IEEE 279-1968.The test procedures require that certain equipment be removed from service by racking out breakers and by pull to stop switches as well as the use of jumpers and removal of fuses discussed above.These test methods violate Section 4.20 of IEEE Std.279-1968 because they are not annunciated to the operator in a timely manner such as to provide him with an unambiguous indication of the status of equipment needed to protect the public health and safety.Response: RGGE requires that, any safety system which is temporarily rendered inoperable due to testing during normal plant operations be monitored by the Ginna"Test Tag Control Program" (Procedure A-1103).A copy of this procedure is included.In addition, any testing, maintenance, or other operation performed on a safety-related piece of equipment at Ginna must be approved by the shift super-visor.Information about the operability of safety-related equipment to control room personnel is thus further assured.I I I I f4~,(1 4.As noted in Topic VI-4 we~have also discovered that the.override of an automati.c ESF actuation signal incapacitates the system level manual actuation features.Response: This concern was addressed in letters from John E.Maier (RGEE)to Dennis M.Crutchfield (NRC)dated March 2, 1981 and September 18, 1981.Resolution of any ad-ditional items is being addressed under SEP Topic VI-4.2 0 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER g)NqP, 87/~7loh UHli<<1 COMPL" TED DATE:-T)MF.:-PROCEDURE NO.A-1402'REV.NO~BYPASS OF SAFETY FUNCTION OR JUMPER CONTROL TECHNICAL REVIEW PORC 4/8/81 QC REVIEW Q.A.REVIEW 0/2 6 II i'i--DATE APPROVED FOR USE LANT SUPERIiNTENDENT DATE QA-NON-QA CATAGORY 1.0 REVIEWED BY'HIS PROCEDURE COiNTAINS 3 PAGES j
| | 3.2.3 The Test Coordinator shall assure the first 4 lines of each test tag is complete and indicate the date the tag is placed. |
| ~,~~A-1402:1 A-1402 BYPASS OF SAFETY FUNCTION OR JUMPER CONTROL 1.0 PURPOSE:-To control the use of jumper.wires, lifted wire, pulled fuses, use of states blocks, spool pieces,-blank flanges, or other means to bypass, defeat or permit a device to perform or not perform its intended function.1.2 This procedure does not apply when the functon is altered as part of an approved maintenance, calibration, test or modification procedure, nor does it apply to use of installed switches or buttons.
| | 3.2.4 Test tags shall be hung at the control switch, valve or other devices. |
| | 3.2.4.1 In the event of an error on a test tag or changes in plant condi-tions which require a correction in test tag initial information, the test co-ordinator will be notified. Upon his concurrence, test personnel shall line out the initial information, insert re-quired new information and initial the correction. |
| | 3.2.5 At the conclusion of the test, and with the permission of the "STATION HOLDING AUTHORITY", test tags shall be removed and status recorded in the Test Control Log. For testing during normal operation, "Test Termination" for safety systems tempor-arily inoperable, shall be when switches, valves and other related devices are returned to their pretest position and the system is again made fully operable. |
| | NOTE: For testing during refueling outages, and if at the conclusion of the test it is agreed to leave a system in its test alignment for subsequent maintenance or inspection, the "STATION HOLDING AUTHORITY" shall transfer control status of boundary valves from "TEST" to Shift upervisor >>HOLD>> as appropriate |
|
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|
| ==2.0 REFERENCES==
| | 'A-1103:3 3.3 Test Control Record Retention |
| : | | ,,i 3.3.1 The Test Control Log is an official record for all test control". |
| 2.1 None 3.0 INSTRUCTIONS:
| | operations and shall be maintained in the iMain Control Room. |
| 3.1 The multileaf request form should normally be initiated by the Job Foreman by signature on the request form.3.1.1 Two knowledgeable individuals, one being the job foreman, shall concur on the location and clearly describe.Terminal point locations, wire number, fuse number, or other description shall be used.3.1.2 3.2 The Job Foreman shall ensure the function and purpose are listed.The Shift Supervisor or alternate shall review the request for safety significance and effects on plant operations to determine whether the request should be approved or disapproved. | | '''''.3.1.1 Completed log sheets will be given to Central Records for 'filing. |
| 3.3 If approved, the Shift Supervisor or alternate shall assign a sequential Request Ik, preceded by the year (i.e., 80-1).Implementation shall be verified by two knowledgeable individuals.
| | 3.3.2 Test tags may be disposed of -after procedure steps requiring~them been completed and the "Restored To Service" section of:,the 'ave Test Control Log has been filled out. |
| I 3.4.1 Identification tags shall be attached to the jumper wire, lifted wire, or other device, as appropriate, to clearly identify the device.NOTE: If it is not feasible to physically attach the tag to the device, the tag should be fastened in the immediate area.3.4.2~~Removal shall be verified by two knowledgeable individuals;
| | 3.4 Plant Emergenc During Testing 3.4.1 If a plant emergency condition should develop during a test, and it is, desirable to lift restraints on a safety system temporarily inoperable because of the test, the Shift Supervisor shall notify . |
| (~~~~A-1402:2 The Official Record shall indicate when this is performed, and when it is removed.3.6 The Shift Supervisor shall review the active binder before a unit startup to ensure plant requirements are met.4.0 RECORDS: 4.1 The multileaf request form original shall remain in the Shift Super-visor's active binder until completed, and then submitted to Central Records.4.2 L The yellow copy shall go to the Job Foreman, and may be destroyed when completed.
| | the Test Coordinator to terminate the test and order the valves, switches or devices restored to their normal position. w / |
| 4.3 Jumper control tag(s)may be destroyed when completed.
| |
| ~~E~~~~'A->402:3 ROCHESTER GAS AND ELECTRIC GINNA STATION RMCRCTTCK PROCCOURC Al&R BYPASS OF SAFETY FUNCTION AND JUMPER CONTROL T JOB FOREMAHT VERIFIED BYT OATEE REQUEST A JUMPER WIRE Q FUNCTION LIFTED WIRE Q FUSES PULLED Q STATES BLOCK Q OTHER Q PURPOSE LOCATION I SHIFT SUPERYISORT DATE>~IHSTLLL TIOII DATE 4 TIME EE~Y DATE 8 TIME ENTERED IH OfFICIAL LOG;NUMBER OF TAGS ISSUED: KHTERED IH OFFICIAI.LOG;NUMBER OF TAG REMOVED: INSTALLED BYT YERIF IED BYT REMOVEO BYT VERIFIED BYT~I T42 A 0 C ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO.A-1103 REV.NO.TEST TAG CONTROL PROGRAM TECHNICAL REVIEW PORC 3/4/81 QC REVIEW DATE APPROVED FOR USE LANT SUPERINTENDENT DATE QA X NON-QA CATAGORY 1.0 REVIEWED BY'HIS PROCEDURE CONTAINS 5 PAGES A-1103:1 A-1103 TEST TAG CONTROL PROGRAM 1.0 PURPOSE:, This procedure describes the test control program for surveillance testing and fo'r"special tests on equipment, systems, and structures under the jurisdiction of the Shift Supervisor.
| |
| 1.2 This procedure'lso provides'a'method for indicating the status of a Nuclear Safety System which is temporarily inoperable because of testing during normal plant operations.
| |
| 2.0
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|
| |
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| ==2.1 REFERENCES==
| | ROCHESTER OAS ANO ELECTRIC CORPORATION GIHHA STATIOH TEST TAG CONTROL LOG TEST POSITION OUT OF SERVICE RESTORED TO SERVICE SAFECUARO TRAIN EQUIPMENT FUSES HOLOINC 'TEST TEST MORE TRACTIVE OFEII CLOSEO AS REO. CATE TIME OATE TINE REMARKS {AS ArrLICAOLEI rULLEO AUTIIORITT COOROINATOR NUMBER |
| 'inna Quality Assurance Manual, Section 14.2.2 Regulatory Guide 1.47"Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety System".3.0 INSTRUCTIONS'.1 Description 3;1.1 A test control program utilizing test tags (See Figure 1)and a test control log (See Figure 2), shall be utilized to provide the status indication and control of systems and equipment involved in the various tests.Valves, switches and other devices included in the test control program shall include: 3.1.1.1 Those major components positioned out of their normal position for the duration of'he test.3.1.1.2 Those boundary valves which are desired to remain closed during the test.3.1.1.3 3.1.1.4 3.1.1.5 Throttling valves under the control of test personnel.
| | . slnS in.<na |
| Critical system valves to remain open during the test.Valves placed out-of-normal alignment during verification of interlock functions need not be tagged if returned to normal position in a minimal amount of time.NOTE: This s stem is not to be confused or used in lace of the regular"Hold" s stem which is for the rotection of e ui ment and personnel.
| | '.NONrFRNANEMT . onrow((oNoATE}} |
| A-1103:2 3.1.2 The."SAFE GUARDS TRAIN MODE INACTIVE" This section of the TEST CONTROL LOG SHEET shall be used to indicate any nuclear safety systems made inoperable for more than 1 hour as a result of the related equipment involved in a test.3.2 3.2.1 Tag Control Procedure Prior to the start of the test, the test coordinator (Qualified Test Personnel Level II or III)shall review the Test Procedure with the"STATION HOLDING AUTHORITY" for test tag requirements after receiving permission to perform the test.3.2.2 3.2.3 All test tags shall be logged in the Test Control Log by the Test Coordinator with each entry to include the following information:
| |
| EQUIPMENT; POSITION DURING TEST;TEST NUMBER;TEST COORDINATOR; PERFORMED BY;DATE AND DATE TEST PERFORMED; SAFEGUARDS TRAIN MODE INACTIVE (AS APPLICABLE)
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| AND STATION HOLDING AUTHORITY.
| |
| The Test Coordinator shall assure the first 4 lines of each test tag is complete and indicate the date the tag is placed.3.2.4 Test tags shall be hung at the control switch, valve or other devices.3.2.4.1 3.2.5 In the event of an error on a test tag or changes in plant condi-tions which require a correction in test tag initial information, the test co-ordinator will be notified.Upon his concurrence, test personnel shall line out the initial information, insert re-quired new information and initial the correction.
| |
| At the conclusion of the test, and with the permission of the"STATION HOLDING AUTHORITY", test tags shall be removed and status recorded in the Test Control Log.For testing during normal operation,"Test Termination" for safety systems tempor-arily inoperable, shall be when switches, valves and other related devices are returned to their pretest position and the system is again made fully operable.NOTE: For testing during refueling outages, and if at the conclusion of the test it is agreed to leave a system in its test alignment for subsequent maintenance or inspection, the"STATION HOLDING AUTHORITY" shall transfer control status of boundary valves from"TEST" to Shift upervisor>>HOLD>>as appropriate
| |
| 'A-1103:3 3.3 Test Control Record Retention 3.3.1 ,,i The Test Control Log is an official record for all test control".operations and shall be maintained in the iMain Control Room.'''''.3.1.1 3.3.2 3.4 Completed log sheets will be given to Central Records for'filing.Test tags may be disposed of-after procedure steps requiring~them
| |
| 'ave been completed and the"Restored To Service" section of:,the Test Control Log has been filled out.Plant Emergenc During Testing 3.4.1 If a plant emergency condition should develop during a test, and*it is, desirable to lift restraints on a safety system temporarily inoperable because of the test, the Shift Supervisor shall notify.the Test Coordinator to terminate the test and order the valves, switches or devices restored to their normal position.w/
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| ROCHESTER OAS ANO ELECTRIC CORPORATION GIHHA STATIOH TEST TAG CONTROL LOG EQUIPMENT TEST POSITION OFEII CLOSEO AS REO.FUSES rULLEO CATE TIME HOLOINC AUTIIORITT | |
| 'TEST COOROINATOR OUT OF SERVICE TEST NUMBER OATE TINE REMARKS RESTORED TO SERVICE SAFECUARO TRAIN MORE TRACTIVE{AS ArrLICAOLEI
| |
| '.NONrFRNANEMT | |
| .onrow{{oNoATE | |
| .slnS in.<na}}
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs IR 05000244/19992011999-09-24024 September 1999 Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L4481990-09-18018 September 1990 Forwards Responses to Rer 900709-13 Team Visit Findings, Per .Responses Withheld (Ref 10CFR73.21) ML17309A4491990-09-13013 September 1990 Forwards Slides Presented by Facility & Westinghouse to NRC in 900724 Meeting.Encl Withheld ML17262A1331990-09-11011 September 1990 Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion ML17261B1511990-08-29029 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Rev 3 to Process Control Program for Ginna Station, Per Tech Specs 6.9.1.4 & 6.16,respectively ML17261B1481990-08-28028 August 1990 Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant IR 05000244/19880261990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1501990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1371990-08-17017 August 1990 Forwards Rev 0 to, Inservice Insp Rept for Third Interval (1990-1999),First Period,First Outage (1990) at Re Ginna Nuclear Power Plant. ML17309A4481990-08-16016 August 1990 Responds to NRC 900717 Ltr Re Violations Noted in Insp Rept 50-244/90-80.Corrective Actions:Westinghouse Drawing E-2508 Approved & Issued to Central Records ML17261B1351990-08-15015 August 1990 Provides Info & Assessment on Integrity of Connection of Containment Bldg to Foundation,Per 900808 Telcon.Util Believes That Existing Condition Not Safety Concern & No Reason Exists to Suspect Joint Will Not Perform Function ML17261B1361990-08-14014 August 1990 Responds to Commitment Tracking Concerns Noted in Insp Rept 50-244/90-09 & Planned Corrective Actions.Util Confirms Commitments Dates for Implementation of Effective Shelf Life Program & Comprehensive Preventive Maint Program for Parts ML17261B1331990-08-13013 August 1990 Recommits to Performing Enhanced primary-to-secondary Leak Rate Monitoring,Per NRC Bulletin 88-002 ML17261B1261990-07-30030 July 1990 Clarifies Commitment Made in 900316 RO Re Restoring Inoperable Fire Damper I-411-21-P.Util Plans to Design Removable Track Which Will Allow Charcoal Drawer to Be Manipulated.Definitive Schedule Will Be Provided in 60 Days ML20055H9291990-07-23023 July 1990 Forwards Revised Page 6:4 of Plant Security Plan.Page Withheld Per 10CFR73.21 ML17261B1091990-07-20020 July 1990 Advises That Structural Evaluations of Containment Sys Being Performed in Response to Containment Integrity Insp ML17309A4471990-07-17017 July 1990 Forwards Decommissioning Rept, for Plant,Per 10CFR50.33(k) & 50.75(b) ML17261B0881990-07-13013 July 1990 Provides Update to Util 860616 Ltr Re Implementation of NUREG-0737,Item 6.2,Suppl 1, Emergency Response Capability. ML17261B0921990-07-11011 July 1990 Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723 ML20044B0481990-07-10010 July 1990 Discusses Review of Station Blackout Documentation,Per 10CFR50.63.Licensee Will Complete Enhancements to Station Blackout Documentation Identified in Attachment 1 as Indicated & Other Items Will Be Completed within 2 Yrs ML17309A4461990-07-0909 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions ML17261B0931990-07-0909 July 1990 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Completed All Actions Requested in Generic Ltr & Will Retain Documentation Verification for Min of 2 Yrs ML17261B0901990-07-0909 July 1990 Advises That Licensee Will Install Containment Isolation Signal Going to Valve AOV 745 by End of 1992 Refueling Outage,Per Util 900608 Ltr Notifying of Condition Outside Design Basis of Plant Under 10CFR50.72 Criterion ML17250B2151990-06-29029 June 1990 Forwards Application for Amend to License DPR-18, Reformatting Auxiliary Electrical Sys Tech Specs & Action Statements for Offsite & Onsite Power Sources Available for Plant Auxiliaries ML17261B0851990-06-28028 June 1990 Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21 ML17250B1991990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-244/89-81.Corrective Actions:Improved Battery Load Profile Developed Incorporating Calculational Improvements Contained in Current Industry Std IEEE 485-1983 ML17250B1951990-06-0505 June 1990 Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept ML17250B1851990-06-0101 June 1990 Forwards Application for Amend to License DPR-18,providing Guidance for Action Statements Associated W/Power Distribution Limit Specs ML17261B0691990-06-0101 June 1990 Discusses Testing Frequency for Insp of Incore Neutron Monitoring Sys Thimble Tubes,Per NRC Bulletin 88-009.Thimble Tube Indicating Greatest Wear Recently Repositioned in Effort to Minimize Future Wear ML17250B1811990-05-31031 May 1990 Forwards Addl Info Re Response to Notice of Violation from Insp Rept 50-244/90-04.Info Withheld (Ref 10CFR73.21) ML17250B1801990-05-29029 May 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Util Does Not Need to Develop Enhanced Surveillance Program to Monitor Currently Installed Transmitter Based Upon Limited Installed Quantity ML17250B1841990-05-29029 May 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined ML17261B0961990-05-29029 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred ML17250B1721990-05-18018 May 1990 Forwards Rev 1 to Summary Exam Rept for 1990 Steam Generator Eddy Current Insp. Rept Summarizes Observations & Corrective Actions Resulting from Insps Performed During 1990 Outage ML20042G8931990-05-0808 May 1990 Forwards Revised Emergency Operating Procedures,Including Rev 3 to AP-RHR.2,Rev 1 to ES-0.3 & Rev 11 to ES-1.3 ML17261B0611990-04-26026 April 1990 Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements ML17261B0591990-04-17017 April 1990 Advises That No Interlocks Required for RHR motor-operated Valves 701 & 720 Based on Present Arrangement.Listed Failures Would Have to Occur in Order for Potential Overpressurization of RHR Sys to Occur ML17261B0461990-04-12012 April 1990 Responds to Issues Discussed During 900323 Telcon Re Inservice Testing Program Status & Relief Request.Current Test Methodology for Seat Leakage Acceptable Based on Application of Direct Measurement Sys ML17262A1431990-04-12012 April 1990 Responds to NRC 900202 Ltr Re Weaknesses Noted in Insp Rept 50-244/89-80.Corrective Actions:Procedure ES-0.3 Modified to Provide Guidance for Rapid Cooldown & Depressurization W/ & W/O Reactor & Vessel Instrumentation Sys ML17250B1451990-04-0606 April 1990 Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed ML17250B1441990-04-0505 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-244/90-02.Corrective Actions:Positive Indicator Will Be Installed for All Check Valves to Enhance Visible Positive Position Verification Ability & to Avoid Confusion ML17261B0401990-03-30030 March 1990 Advises That Final Results of Station Blackout Documentation Review Will Be Submitted to NRC on or About 900501 ML17261B0321990-03-28028 March 1990 Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp ML17261B0331990-03-28028 March 1990 Forwards Info Re Reactor Vessel Issues,Per 900305 Telcon Concerning Change of License Expiration Date ML17261B0231990-03-26026 March 1990 Responds to NRC 890222 Ltr Re Violations Noted in Insp Rept 50-244/89-17.Corrective Actions:Personnel Verified Safety Injection Block/Unblock Switch in Proper Position & Operator Procedure 0-1.1 Changed as Indicated ML17261B0281990-03-23023 March 1990 Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods ML17261B0221990-03-22022 March 1990 Provides Revised Test Schedule for motor-operated Valve Diagnostic Test Program,Per IE Bulletin 85-003.NRC Notification of Changes to Valve Operability Program Required by Generic Ltr 89-10,dtd 890828 ML17261B0411990-03-20020 March 1990 Forwards Summary of Onsite Property Damage Coverage Currently in Force at Plant,Per 10CFR50.54(w)(4) ML17261B0151990-03-19019 March 1990 Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Plants (USI A-47). Overfill Protection Provided Through Trip Bistables in Reactor Protection Racks Powered from 120-volt Instrument Buses ML17261B0101990-03-15015 March 1990 Forwards Application for Amend to License DPR-18,allowing Use of Reconstituted Fuel Assemblies ML20012D2831990-03-14014 March 1990 Responds to Issues Discussed During 900307 Telcon W/Util & Eg&G Re Inservice Testing Program Status & Relief Request. Valves 5960A & 5960B Will Be Disassembled to Verify Forward Flow.Relief Requests PR-8 & VR-25 Encl 1990-09-18
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'Im'uit ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER, N.Y. I4649 JOHN E. MA IER TCL,EPHONE VICE PRESIDENT ARCA cOOK Tld 546-2700 September 25, 1981 Director of Nuclear Reactor Regulation Attention: Mr. Dennis M. Crutchf ield, Chief Operating Reactors Branch 55 gag '-g);
U. S. Nuclear Regulatory Commission Washington, D.C. 20555 1981~ 12 graf Ij~g~ Nlgj
Subject:
SEP Topics VI-7.A.3 and VI-10.A R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
This letter is in response to your letter of December 15, 1980, transmitting the final SEP assessments for these two topics to Rochester Gas and Electric. Four items requiring resolution during the Integrated Assessment for Ginna were identified in these assessments. The information in the enclosure should resolve these concerns prior to the Integrated Assessment.
Very truly yours, hn E. Maier Enclosure
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Enclosure:
RG&E Responses to Concerns Identified in the Evaluation and Conclusions of the SEP Assessment for SEP Topics VI-7.A.3 and VI-10.A, 12/15/80
- 1. The instrumentation strings from sensors thru bistable devices are not response time tested. As a result, the testing required by IEEE Std. 279-1968 Section 4.10 is not satisfied because the response time design basis (IEEE 279-1968 Section 3 (i)) is not verified.
Response: RG&E does not, at this time perform response time testing of instrumentation strings for the Engineered Safety Feature System. We disagree, however, that the lack of such testing violates the provisions of IEEE 279-1968.
RG&E does perform testing to verify that the final actuated devices are properly operational within the times assumed in the plant design basis. Appropriate test procedures were sent to the NRC with RG&E's trans-mittal of September 10, 1980.
The Ginna design does not conform with the provisions of Regulatory Guide 1.118, "Periodic Testing of Electric Power and Protection Systems." This regulatory guide was published long after Ginna became operational; it was thus obviously not considered in the design of the plant. The latest version of Regulatory Guide 1.118 (Rev. 2 published June 1978), states that this regulatory guide ". . . is'being and will continue to be used in the evaluation of submittals in connection with Construction Permit a lications . . ." (emphasis added). The implementation of this regulatory guide does not provide specific provisions for backfitting; it is not directly applicable to Ginna. RG&E further does not believe that strict adherence to the guidance provided in Regulatory Guide 1.118 is necessary to meet IEEE-279-1968 requirements. RG&E performs periodic tests and calibration on all components of the protection system instrumentation strings, including sensors. Any significant degradation in component response will be identified and corrected by this activity. RG&E is also preparing to implement certain response time testing at the Ginna plant. Ginna Technical Specifi-cations 4.4.6.2 and 4.8.10 require that the response time of each containment isolation function and each auxiliary feedwater initiation function be demonstrated to be within required limits at least once per 18 months. RG&E is presently developing a program to effect this requirement.
It is considered that the current methodology meets the requirements of this SEP topic. This issue does not need to be considered further within the Systematic Evaluation Program.
1 M
- 2. The test procedures required the removal of fuses and installation of jumpers to block equipment operation and/or to simulate contact closure. The procedures often do not specify the time at which these jury-rigged modifications are removed. This situation is a violation of IEEE,Std.
279-1968 Sections 4.13 and 4.20.
Response: RGGE is unclear as to how this conclusion was drawn from a review of the Ginna test procedures. When the removal of fuses and installation of jumpers to block equipment operation and'/or 'simulate contact closure is required as part of a test procedure, the alignment of this equipment to its original configuration is also specified in the procedure.
If the use of jumper control is needed, when is not directly specified in an approved maintenance, cali-it bration, test, or modification procedure, procedure A-1402, "Bypass of Safety Function or Jumper Control" is used. Installation and removal of any such jumpers is performed by two knowledgeable individuals, one being the job foreman. A copy of this procedure, Rev.
1, is attached.
RG&E thus considers the procedures for use of jumpers and fuses acceptable, and in conformance with IEEE 279-1968.
The test procedures require that certain equipment be removed from service by racking out breakers and by pull to stop switches as well as the use of jumpers and removal of fuses discussed above. These test methods violate Section 4.20 of IEEE Std. 279-1968 because they are not annunciated to the operator in a timely manner such as to provide him with an unambiguous indication of the status of equipment needed to protect the public health and safety.
Response: RGGE requires that, any safety system which is temporarily rendered inoperable due to testing during normal plant operations be monitored by the Ginna "Test Tag Control Program" (Procedure A-1103). A copy of this procedure is included. In addition, any testing, maintenance, or other operation performed on a safety-related piece of equipment at Ginna must be approved by the shift super-visor. Information about the operability of safety-related equipment to control room personnel is thus further assured. I I 1
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- 4. As noted in Topic VI-4 we have also discovered
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override of an automati.c ESF actuation signal incapacitates the system level manual actuation features.
Response: This concern was addressed in letters from John E. Maier (RGEE) to Dennis M. Crutchfield (NRC) dated March 2, 1981 and September 18, 1981. Resolution of any ad-ditional items is being addressed under SEP Topic VI-4.
2
0 g)NqP, 87/~7loh UHli <<1 COMPL" TED ROCHESTER GAS AND ELECTRIC CORPORATION DATE:-
GINNA STATION T)MF.:-
CONTROLLED COPY NUMBER PROCEDURE NO. A-1402 'REV. NO ~
BYPASS OF SAFETY FUNCTION OR JUMPER CONTROL TECHNICAL REVIEW PORC 4/8/81 Q. A. REVIEW QC REVIEW 0 /2 6 II i'i-- DATE APPROVED FOR USE LANT SUPERIiNTENDENT DATE QA- NON-QA CATAGORY 1.0 REVIEWED BY
'HIS PROCEDURE COiNTAINS 3 PAGES
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A-1402:1 A-1402 BYPASS OF SAFETY FUNCTION OR JUMPER CONTROL
1.0 PURPOSE
To control the use of jumper. wires, lifted wire, pulled fuses, use of states blocks, spool pieces, -blank flanges, or other means to bypass, defeat or permit a device to perform or not perform its intended function.
1.2 This procedure does not apply when the functon is altered as part of an approved maintenance, calibration, test or modification procedure, nor does it apply to use of installed switches or buttons.
2.0 REFERENCES
2.1 None
3.0 INSTRUCTIONS
3.1 The multileaf request form should normally be initiated by the Job Foreman by signature on the request form.
3.1. 1 Two knowledgeable individuals, one being the job foreman, shall concur on the location and clearly describe. Terminal point locations, wire number, fuse number, or other description shall be used.
3.1.2 The Job Foreman shall ensure the function and purpose are listed.
3.2 The Shift Supervisor or alternate shall review the request for safety significance and effects on plant operations to determine whether the request should be approved or disapproved.
3.3 If approved, the Shift Supervisor or alternate shall assign a sequential Request Ik, preceded by the year (i.e., 80-1).
Implementation shall be verified by two knowledgeable individuals.
I 3.4.1 Identification tags shall be attached to the jumper wire, lifted wire, or other device, as appropriate, to clearly identify the device.
NOTE: If it is not feasible to physically attach the tag to the device, the tag should be fastened in the immediate area.
3.4.2
~ ~ Removal shall be verified by two knowledgeable individuals;
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A-1402:2 The Official Record shall indicate when this is performed, and when it is removed.
3.6 The Shift Supervisor shall review the active binder before a unit startup to ensure plant requirements are met.
4.0 RECORDS
4.1 The multileaf request form original shall remain in the Shift Super-visor's active binder until completed, and then submitted to Central Records.
L 4.2 The yellow copy shall go to the Job Foreman, and may be destroyed when completed.
4.3 Jumper control tag(s) may be destroyed when completed.
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ROCHESTER GAS AND ELECTRIC RMCRCTTCK PROCCOURC Al&R GINNA STATION BYPASS OF SAFETY FUNCTION AND JUMPER CONTROL T
JOB FOREMAHT OATEE REQUEST A VERIFIED BYT JUMPER WIRE Q LIFTED WIRE Q FUSES PULLED Q STATES BLOCK Q OTHER Q FUNCTION PURPOSE LOCATIONI SHIFT SUPERYISORT DATE>
~IHSTLLL TIOII EE~Y DATE 4 TIME DATE 8 TIME ENTERED IH OfFICIAL LOG; KHTERED IH OFFICIAI. LOG; NUMBER OF TAGS ISSUED: NUMBER OF TAG REMOVED:
INSTALLED BYT REMOVEO BYT YERIF IED BYT VERIFIED BYT
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0 C ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER PROCEDURE NO. A-1103 REV. NO.
TEST TAG CONTROL PROGRAM TECHNICAL REVIEW PORC 3/4/81 QC REVIEW DATE APPROVED FOR USE LANT SUPERINTENDENT DATE QA X NON-QA CATAGORY 1.0 REVIEWED BY'HIS PROCEDURE CONTAINS 5 PAGES
A-1103:1 A-1103 TEST TAG CONTROL PROGRAM 1.0 PURPOSE:,
This procedure describes the test control program for surveillance testing and fo'r "special tests on equipment, systems, and structures under the jurisdiction of the Shift Supervisor.
1.2 This procedure'lso provides'a'method for indicating the status of a Nuclear Safety System which is temporarily inoperable because of testing during normal plant operations.
2.0 REFERENCES
'inna 2.1 Quality Assurance Manual, Section 14.
2.2 Regulatory Guide 1.47 "Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety System".
3.0 INSTRUCTIONS'.1 Description 3;1.1 A test control program utilizing test tags (See Figure 1) and a test control log (See Figure 2), shall be utilized to provide the status indication and control of systems and equipment involved in the various tests. Valves, switches and other devices included in the test control program shall include:
3.1.1.1 Those major components positioned out of their normal position for the duration of'he test.
3.1.1.2 Those boundary valves which are desired to remain closed during the test.
3.1.1.3 Throttling valves under the control of test personnel.
3.1.1.4 Critical system valves to remain open during the test.
3.1.1.5 Valves placed out-of-normal alignment during verification of interlock functions need not be tagged if returned to normal position in a minimal amount of time.
NOTE: This s stem is not to be confused or used in lace of the regular "Hold" s stem which is for the rotection of e ui ment and personnel.
A-1103:2
- 3. 1.2 The. "SAFE GUARDS TRAIN MODE INACTIVE" This section of the TEST CONTROL LOG SHEET shall be used to indicate any nuclear safety systems made inoperable for more than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> as a result of the related equipment involved in a test.
3.2 Tag Control Procedure 3.2.1 Prior to the start of the test, the test coordinator (Qualified Test Personnel Level II or III) shall review the Test Procedure with the "STATION HOLDING AUTHORITY" for test tag requirements after receiving permission to perform the test.
3.2.2 All test tags shall be logged in the Test Control Log by the Test Coordinator with each entry to include the following information:
EQUIPMENT; POSITION DURING TEST; TEST NUMBER; TEST COORDINATOR; PERFORMED BY; DATE AND DATE TEST PERFORMED; SAFEGUARDS TRAIN MODE INACTIVE (AS APPLICABLE) AND STATION HOLDING AUTHORITY.
3.2.3 The Test Coordinator shall assure the first 4 lines of each test tag is complete and indicate the date the tag is placed.
3.2.4 Test tags shall be hung at the control switch, valve or other devices.
3.2.4.1 In the event of an error on a test tag or changes in plant condi-tions which require a correction in test tag initial information, the test co-ordinator will be notified. Upon his concurrence, test personnel shall line out the initial information, insert re-quired new information and initial the correction.
3.2.5 At the conclusion of the test, and with the permission of the "STATION HOLDING AUTHORITY", test tags shall be removed and status recorded in the Test Control Log. For testing during normal operation, "Test Termination" for safety systems tempor-arily inoperable, shall be when switches, valves and other related devices are returned to their pretest position and the system is again made fully operable.
NOTE: For testing during refueling outages, and if at the conclusion of the test it is agreed to leave a system in its test alignment for subsequent maintenance or inspection, the "STATION HOLDING AUTHORITY" shall transfer control status of boundary valves from "TEST" to Shift upervisor >>HOLD>> as appropriate
'A-1103:3 3.3 Test Control Record Retention
,,i 3.3.1 The Test Control Log is an official record for all test control".
operations and shall be maintained in the iMain Control Room.
.3.1.1 Completed log sheets will be given to Central Records for 'filing.
3.3.2 Test tags may be disposed of -after procedure steps requiring~them been completed and the "Restored To Service" section of:,the 'ave Test Control Log has been filled out.
3.4 Plant Emergenc During Testing 3.4.1 If a plant emergency condition should develop during a test, and it is, desirable to lift restraints on a safety system temporarily inoperable because of the test, the Shift Supervisor shall notify .
the Test Coordinator to terminate the test and order the valves, switches or devices restored to their normal position. w /
ROCHESTER OAS ANO ELECTRIC CORPORATION GIHHA STATIOH TEST TAG CONTROL LOG TEST POSITION OUT OF SERVICE RESTORED TO SERVICE SAFECUARO TRAIN EQUIPMENT FUSES HOLOINC 'TEST TEST MORE TRACTIVE OFEII CLOSEO AS REO. CATE TIME OATE TINE REMARKS {AS ArrLICAOLEI rULLEO AUTIIORITT COOROINATOR NUMBER
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