ML18141A569: Difference between revisions
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| issue date = 03/30/1984 | | issue date = 03/30/1984 | ||
| title = Responds to 840221 & 28 Telcons Requesting Addl Info Required to Complete Franklin Research Ctr Review of Util Submittal for Conformance to NUREG-0612, Control of Heavy Loads Phase I. | | title = Responds to 840221 & 28 Telcons Requesting Addl Info Required to Complete Franklin Research Ctr Review of Util Submittal for Conformance to NUREG-0612, Control of Heavy Loads Phase I. | ||
| author name = | | author name = Stewart W | ||
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) | ||
| addressee name = | | addressee name = Denton H, Varga S | ||
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | | addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR) | ||
| docket = 05000280, 05000281 | | docket = 05000280, 05000281 | ||
| Line 17: | Line 17: | ||
=Text= | =Text= | ||
{{#Wiki_filter:W. L. STEWA.:QT VICE PRESIDENT | {{#Wiki_filter:e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWA.:QT VICE PRESIDENT March 30, 1984 NUCLEAR OPERATIONS Mr. Harold R. Denton, Director Serial No. 162 Office of Nuclear Reactor Regulation E&C/TLG: | ||
Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U.S. Nuclear Regulatory Commission DPR-37 Washington, DC 20555 NUREG 0612 - CONTROL OF HEAVY LOADS PHASE I SURRY POWER STATION UNITS 1 AND 2 Gentlemen: | |||
NUREG 0612 -CONTROL OF HEAVY LOADS PHASE I SURRY POWER STATION UNITS 1 AND 2 In response to your February 21, 1984 and February 28, 1984 telephone request for additional information required to complete Franklin Research Center's (FRC) review of Vepco | In response to your February 21, 1984 and February 28, 1984 telephone request for additional information required to complete Franklin Research Center's (FRC) review of Vepco s submittal for Surry Power Station Units 1 and 2 1 | ||
conformance to NUREG-0612 11 Control of Heavy Loads at Nuclear Power Plants 11 Phase I, the following is provided. | |||
SPECIAL LIFTING DEVICES [GUIDELINE AND NUREG-0612, SECTION 5.1.1(4)] | SPECIAL LIFTING DEVICES [GUIDELINE AND NUREG-0612, SECTION 5.1.1(4)] | ||
ANSI Nl4.6 Section 5.3 requires verification of continuing compliance of the special lifting devices by either annual load test at 150 percent of maximum load or non-destructive testing and dimensional visual examination of the major load carrying welds and critical areas. As previously stated in Vepco | ANSI Nl4.6 Section 5.3 requires verification of continuing compliance of the special lifting devices by either annual load test at 150 percent of maximum load or non-destructive testing and dimensional visual examination of the major load carrying welds and critical areas. As previously stated in Vepco s letter dated July 26, 1983 (Serial Number 325), these tests are 1 | ||
However, Maintenance Procedures require the reactor vessel head and internals lift rigs to be visually inspected prior to each refueling and at each containment maintenance period if they are to be used and have been idle for a period of more than six months or the last inspection has been over one year. Visual inspection of the reactor coolant pump motor lifting rig is required prior to each refueling and at each containment maintenance period if they are to be used and the last inspection has been over one month. All critical welds and bolted joints or connections are inspected during this time and the results are documented per the appropriate procedures. | impractical to perform because the devices are located in the containment. | ||
It was also noted that a load cell is used with the reactor vessel head and internals lift rigs for continued monitoring during all lifting and lowering. | However, Maintenance Procedures require the reactor vessel head and internals lift rigs to be visually inspected prior to each refueling and at each containment maintenance period if they are to be used and have been idle for a period of more than six months or the last inspection has been over one year. Visual inspection of the reactor coolant pump motor lifting rig is required prior to each refueling and at each containment maintenance period if they are to be used and the last inspection has been over one month. All critical welds and bolted joints or connections are inspected during this time and the results are documented per the appropriate procedures. It was also noted that a load cell is used with the reactor vessel head and internals lift rigs for continued monitoring during all lifting and lowering. | ||
This approach is consistent with Westinghouse's (the designer, fabricator and supplier) recommendations. | This approach is consistent with Westinghouse's (the designer, fabricator and supplier) recommendations. | ||
f1o33 1/ I) e | f1o33 1/ I) | ||
ELECTRIC AND POWER COMPANY TO It was Vepco 1 s intention that through the use of procedural requirements and controls for visual inspection and documentation prior to use, continued load cell monitoring during all lifting and lowering operations, the simplicity and specific designs of the rigs, and the infrequent use of the rig, the intent of ANSI Nl4.6 -1978 for continuing compliance would be sufficiently met. However, in order to ensure a higher level of confidence and acceptability in demonstrating the continued reliability of the special lifting rigs and continuing compliance with ANSI Nl4.6 -1978, further investigations, discussions and reviews of these procedures and controls were performed. | e VIRGINIA. ELECTRIC AND POWER COMPANY TO It was Vepco 1 s intention that through the use of procedural requirements and controls for visual inspection and documentation prior to use, continued load cell monitoring during all lifting and lowering operations, the simplicity and specific designs of the rigs, and the infrequent use of the rig, the intent of ANSI Nl4.6 - 1978 for continuing compliance would be sufficiently met. However, in order to ensure a higher level of confidence and acceptability in demonstrating the continued reliability of the special lifting rigs and continuing compliance with ANSI Nl4.6 - 1978, further investigations, discussions and reviews of these procedures and controls were performed. As a result, Vepco has taken action to establish a Non Destructive Examination (NOE) Program in addition to the existing procedural requirements and controls. | ||
As a result, Vepco has taken action to establish a Non Destructive Examination (NOE) Program in addition to the existing procedural requirements and controls. | The NOE Program is being developed and will be incorporated into and as part of Surry 1 s Inservice Inspection Program. The new program shall provide for inspection and NOE of all critical welds and critical parts of the subject special lifting devices over a normal inservice inspection of 10 years. | ||
The NOE Program is being developed and will be incorporated into and as part of Surry 1 s Inservice Inspection Program. The new program shall provide for inspection and NOE of all critical welds and critical parts of the subject special lifting devices over a normal inservice inspection of 10 years. Surry has reviewed the existing operating and maintenance procedures to ensure the appropriate visual inspections and controls are in place. Procedures are now being re-reviewed to incorporate any additional inspections and/or hold points which may be required by any new prior-to-use inspection and the 10 year NOE Program being established. | Surry has reviewed the existing operating and maintenance procedures to ensure the appropriate visual inspections and controls are in place. | ||
Any procedures which are effected or required by the new NOE program will be completed and in effect by the next refueling outage or movement of any heavy load should it occur before the outage. ANSI N14.6 Section 5.2.1 requires each rig to be load tested at 150 percent maximum load prior to its initial use. As previously stated, the reactor vessel head lifting rig had load and lift tests of 100 percent performed, followed by the appropriate non-destructive testing. Westinghouse (designer, fabricator and supplier) did not require load testing of the reactor vessel, internals lift rig and the reactor coolant pump motor lift rig, however, load tests were performed on these two devices as stated. The percent of load used for load testing of the reactor vessel internals lift rig and the reactor coolant pump motor lift rig was investigated. | Procedures are now being re-reviewed to incorporate any additional inspections and/or hold points which may be required by any new prior-to-use inspection and the 10 year NOE Program being established. Any procedures which are effected or required by the new NOE program will be completed and in effect by the next refueling outage or movement of any heavy load should it occur before the outage. | ||
Indications are that these two rigs were load tested at 100 percent of load, however, no official documentation has been found to support and verify the percent of load used. It should be noted that each of these rigs has been used only as designed and for its specific function. | ANSI N14.6 Section 5.2.1 requires each rig to be load tested at 150 percent maximum load prior to its initial use. As previously stated, the reactor vessel head lifting rig had load and lift tests of 100 percent performed, followed by the appropriate non-destructive testing. Westinghouse (designer, fabricator and supplier) did not require load testing of the reactor vessel, internals lift rig and the reactor coolant pump motor lift rig, however, load tests were performed on these two devices as stated. | ||
Further investigation of records is continuing in an attempt to find the testing documentation for the two rigs, however, at this time no documentation is available. | The percent of load used for load testing of the reactor vessel internals lift rig and the reactor coolant pump motor lift rig was investigated. | ||
Indications are that these two rigs were load tested at 100 percent of load, however, no official documentation has been found to support and verify the percent of load used. It should be noted that each of these rigs has been used only as designed and for its specific function. Further investigation of records is continuing in an attempt to find the testing documentation for the two rigs, however, at this time no documentation is available. | |||
This letter should provide the information necessary to complete the Phase I review. cc: Mr. James P. 0 1 | |||
~I VIRGINIA ELECTRIC AND POWER COMPANY TO Measures taken by Vepco to control and monitor the use and maintenance of the special lifting devices are believed to be more than adequate to satisfy the intent of NUREG-0612 and ANSI Nl4.6 - 1978 requirements. This letter should provide the information necessary to complete the Phase I review. | |||
Very truly yours, t)c_w~ | |||
W. L. stew~~'t cc: Mr. James P. 0 Reilly 1 | |||
Regional Administrator Region II Atlanta, Georgia 30303 Mr. Donald J. Burke NRC Resident Inspector Surry Power Station}} | |||
Latest revision as of 23:46, 2 February 2020
| ML18141A569 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/30/1984 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 162, NUDOCS 8404060036 | |
| Download: ML18141A569 (3) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWA.:QT VICE PRESIDENT March 30, 1984 NUCLEAR OPERATIONS Mr. Harold R. Denton, Director Serial No. 162 Office of Nuclear Reactor Regulation E&C/TLG:
Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U.S. Nuclear Regulatory Commission DPR-37 Washington, DC 20555 NUREG 0612 - CONTROL OF HEAVY LOADS PHASE I SURRY POWER STATION UNITS 1 AND 2 Gentlemen:
In response to your February 21, 1984 and February 28, 1984 telephone request for additional information required to complete Franklin Research Center's (FRC) review of Vepco s submittal for Surry Power Station Units 1 and 2 1
conformance to NUREG-0612 11 Control of Heavy Loads at Nuclear Power Plants 11 Phase I, the following is provided.
SPECIAL LIFTING DEVICES [GUIDELINE AND NUREG-0612, SECTION 5.1.1(4)]
ANSI Nl4.6 Section 5.3 requires verification of continuing compliance of the special lifting devices by either annual load test at 150 percent of maximum load or non-destructive testing and dimensional visual examination of the major load carrying welds and critical areas. As previously stated in Vepco s letter dated July 26, 1983 (Serial Number 325), these tests are 1
impractical to perform because the devices are located in the containment.
However, Maintenance Procedures require the reactor vessel head and internals lift rigs to be visually inspected prior to each refueling and at each containment maintenance period if they are to be used and have been idle for a period of more than six months or the last inspection has been over one year. Visual inspection of the reactor coolant pump motor lifting rig is required prior to each refueling and at each containment maintenance period if they are to be used and the last inspection has been over one month. All critical welds and bolted joints or connections are inspected during this time and the results are documented per the appropriate procedures. It was also noted that a load cell is used with the reactor vessel head and internals lift rigs for continued monitoring during all lifting and lowering.
This approach is consistent with Westinghouse's (the designer, fabricator and supplier) recommendations.
f1o33 1/ I)
e VIRGINIA. ELECTRIC AND POWER COMPANY TO It was Vepco 1 s intention that through the use of procedural requirements and controls for visual inspection and documentation prior to use, continued load cell monitoring during all lifting and lowering operations, the simplicity and specific designs of the rigs, and the infrequent use of the rig, the intent of ANSI Nl4.6 - 1978 for continuing compliance would be sufficiently met. However, in order to ensure a higher level of confidence and acceptability in demonstrating the continued reliability of the special lifting rigs and continuing compliance with ANSI Nl4.6 - 1978, further investigations, discussions and reviews of these procedures and controls were performed. As a result, Vepco has taken action to establish a Non Destructive Examination (NOE) Program in addition to the existing procedural requirements and controls.
The NOE Program is being developed and will be incorporated into and as part of Surry 1 s Inservice Inspection Program. The new program shall provide for inspection and NOE of all critical welds and critical parts of the subject special lifting devices over a normal inservice inspection of 10 years.
Surry has reviewed the existing operating and maintenance procedures to ensure the appropriate visual inspections and controls are in place.
Procedures are now being re-reviewed to incorporate any additional inspections and/or hold points which may be required by any new prior-to-use inspection and the 10 year NOE Program being established. Any procedures which are effected or required by the new NOE program will be completed and in effect by the next refueling outage or movement of any heavy load should it occur before the outage.
ANSI N14.6 Section 5.2.1 requires each rig to be load tested at 150 percent maximum load prior to its initial use. As previously stated, the reactor vessel head lifting rig had load and lift tests of 100 percent performed, followed by the appropriate non-destructive testing. Westinghouse (designer, fabricator and supplier) did not require load testing of the reactor vessel, internals lift rig and the reactor coolant pump motor lift rig, however, load tests were performed on these two devices as stated.
The percent of load used for load testing of the reactor vessel internals lift rig and the reactor coolant pump motor lift rig was investigated.
Indications are that these two rigs were load tested at 100 percent of load, however, no official documentation has been found to support and verify the percent of load used. It should be noted that each of these rigs has been used only as designed and for its specific function. Further investigation of records is continuing in an attempt to find the testing documentation for the two rigs, however, at this time no documentation is available.
~I VIRGINIA ELECTRIC AND POWER COMPANY TO Measures taken by Vepco to control and monitor the use and maintenance of the special lifting devices are believed to be more than adequate to satisfy the intent of NUREG-0612 and ANSI Nl4.6 - 1978 requirements. This letter should provide the information necessary to complete the Phase I review.
Very truly yours, t)c_w~
W. L. stew~~'t cc: Mr. James P. 0 Reilly 1
Regional Administrator Region II Atlanta, Georgia 30303 Mr. Donald J. Burke NRC Resident Inspector Surry Power Station