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| {{#Wiki_filter:"-UNITED STATES NUCLEAR REGULATORY | | {{#Wiki_filter:"- |
| | UNITED STATES |
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| COMMISSION | | NUCLEAR REGULATORY COMMISSION |
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| ===OFFICE OF NUCLEAR REACTOR REGULATION===
| | OFFICE OF NUCLEAR REACTOR REGULATION |
| WASHINGTON, D.C. 20555 June 9, 1993 NRC INFORMATION
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| NOTICE 93-42: FAILURE OF ANTI-ROTATION | | WASHINGTON, D.C. 20555 June 9, 1993 NRC INFORMATION NOTICE 93-42: FAILURE OF ANTI-ROTATION KEYS IN MOTOR-OPERATED |
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| KEYS IN MOTOR-OPERATED
| | VALVES MANUFACTURED BY VELAN |
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| VALVES MANUFACTURED | |
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| BY VELAN | |
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| ==Addressees== | | ==Addressees== |
| All holders of operating | | All holders of operating licenses or construction permits for nuclear power |
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| licenses or construction
| | reactors. |
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| permits for nuclear power reactors.
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| ==Purpose== | | ==Purpose== |
| The U.S. Nuclear Regulatory | | The U.S. Nuclear Regulatory Commission (NRC) is issuing this information of |
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| Commission (NRC) is issuing this information
| | notice to alert addressees to potential problems resulting from the failure |
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| notice to alert addressees
| | anti-rotation keys in motor-operated globe valves manufactured by Velan forValve |
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| to potential | | Corporation. It is expected that recipients will review the information to |
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| problems resulting | | applicability to their facilities and consider actions, as appropriate, avoid similar problems. However, suggestions contained in this information or |
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| from the failure of anti-rotation
| | notice do not constitute NRC requirements; therefore, no specific action |
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| keys in motor-operated
| | written response is required. |
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| globe valves manufactured
| | ==Description of Circumstances== |
| | On March 28, 1993, Wisconsin Public Service Corporation, the licensee for |
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| by Velan Valve Corporation.
| | Kewaunee Nuclear Power Plant, reported that during motor-operated valve (MOV) |
| | dynamic testing on March 27, 1993, one of two redundant safety injection |
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| It is expected that recipients
| | recirculation valves to the refueling water storage tank failed to close |
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| will review the information
| | completely. Investigation revealed that the anti-rotation device, an L-shaped |
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| for applicability
| | key between the valve stem and the yoke bushing (Attachment 1), had broken. |
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| to their facilities
| | The shorter part of the broken L-shaped key had apparently worked its way The |
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| and consider actions, as appropriate, to avoid similar problems. | | toward the valve stem and had jammed the valve stem, preventing closing. |
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| However, suggestions
| | valve that failed was a 2-inch bonnetless globe valve manufactured by Velan and |
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| contained
| | Valve Corp. The licensee inspected all nine similar motor-operated valves and |
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| in this information
| | found that six had broken anti-rotation keys. The inspections were visual can |
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| notice do not constitute
| | did not require disassembly of the motor-operated valve. Failures usually |
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| NRC requirements;
| | be observed on normally closed valves, since the broken long leg of the |
| therefore, no specific action or written response is required.Description
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| of Circumstances
| | L-shaped key slides down partially and becomes visible below the yoke bushing. |
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| On March 28, 1993, Wisconsin
| | According to the licensee, the keys failed in a brittle manner. The fractures |
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| Public Service Corporation, the licensee for Kewaunee Nuclear Power Plant, reported that during motor-operated
| | began on either side of the key at the sharp radius of the inside corner of |
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| valve (MOV)dynamic testing on March 27, 1993, one of two redundant
| | the L-shaped key and propagated into the body of the key. Machining of the |
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| safety injection recirculation
| | sharp inside corner of the L-shaped key may have contributed to the failure of |
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| valves to the refueling
| | the anti-rotation keys by producing high stresses in the corner of the keys. |
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| water storage tank failed to close completely.
| | It is likely that the rotational action of the valve stem impacted on both |
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| Investigation
| | sides of the key, exceeding the impact strength of the material at the sharp |
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| revealed that the anti-rotation
| | radius of the key. |
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| device, an L-shaped key between the valve stem and the yoke bushing (Attachment
| | 9306030147 POR SIE Wr;c-c 913o0&i 93o0wt |
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| 1), had broken.The shorter part of the broken L-shaped key had apparently
| | 41 'C1301q3 in le- // A |
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| worked its way toward the valve stem and had jammed the valve stem, preventing
| | IN 93-42 June 9, 1993 In 1990, at the Maine Yankee Atomic Power Station, anti-rotation |
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| closing. The valve that failed was a 2-inch bonnetless
| | 4-inch MOVs manufactured by Velan failed. Maine Yankee keys in |
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| globe valve manufactured
| | the licensee, discovered that spare keys supplied by Atomic Power Company, valves were not of the proper hardness; they were RockwellVelan for several of the |
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| by Velan Valve Corp. The licensee inspected
| | harder Rockwell C-59 as originally specified. Valves C-20 instead of the |
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| all nine similar motor-operated
| | wrong anti-rotation keys installed were disassembled, that may have had the |
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| valves and found that six had broken anti-rotation
| | replaced the Rockwell C-20 keys with keys made of the and the licensee |
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| keys. The inspections | | non-conforming keys that were removed showed signs correct material. The |
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| were visual and did not require disassembly
| | During post-maintenance testing, several of the new of significant wear. |
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| of the motor-operated | | the corner of the 'L" shape. This happened because (hardened) keys broke at |
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| valve. Failures usually can be observed on normally closed valves, since the broken long leg of the L-shaped key slides down partially
| | the |
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| and becomes visible below the yoke bushing.According
| | adaptor plate was too tight considering the service-related keyway in the valve |
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| to the licensee, the keys failed in a brittle manner. The fractures began on either side of the key at the sharp radius of the inside corner of the L-shaped key and propagated | | occurred to the rest of the keyway. Maine Yankee engineers wear that had |
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| into the body of the key. Machining
| | larger keyways should be cut in the adaptor plate to specified that new |
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| of the sharp inside corner of the L-shaped key may have contributed
| | breaking when the valve is actuated. The licensee prevent the key from |
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| to the failure of the anti-rotation | | valves and then tested the valves to ensure that they repaired all the affected |
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| keys by producing
| | operated satisfactorily. |
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| high stresses in the corner of the keys.It is likely that the rotational
| | Before testing MOYs at Prairie Island this past winter, globe valves also discovered anti-rotation key failures an inspection of Velan |
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| action of the valve stem impacted on both sides of the key, exceeding
| | in 16 valves) in similar systems. Because of the (2 broken keys found |
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| the impact strength of the material at the sharp radius of the key.9306030147 POR SIE Wr;c-c 913o0&i 93o0wt 41 ' C1301q3 in le- // A
| | location of the break on the |
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| IN 93-42 June 9, 1993 In 1990, at the Maine Yankee Atomic Power Station, anti-rotation
| | anti-rotation key, and the length of the key and key |
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| keys in 4-inch MOVs manufactured
| | Power Company, the licensee, believed that the broken slot, Northern States |
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| by Velan failed. Maine Yankee Atomic Power Company, the licensee, discovered
| | still perform their intended function and that the anti-rotation keys would |
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| that spare keys supplied by Velan for several of the valves were not of the proper hardness;
| | short leg of the L-shaped key) would not interact broken piece (i.e., the |
| they were Rockwell C-20 instead of the harder Rockwell C-59 as originally
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| specified.
| | impede valve operation. This is at variance with with the valve stem so as to |
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| Valves that may have had the wrong anti-rotation
| | above. The licensee added a step to their generic the Kewaunee event discussed |
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| keys installed
| | procedure to inspect, clean, debur, and lubricate actuator replacement |
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| were disassembled, and the licensee replaced the Rockwell C-20 keys with keys made of the correct material.
| | anti-rotation devices. |
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| The non-conforming
| | Discussion |
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| keys that were removed showed signs of significant
| | On April 5, 1993, Velan issued the attached (Attachment |
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| wear.During post-maintenance
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| testing, several of the new (hardened)
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| keys broke at the corner of the 'L" shape. This happened because the keyway in the valve adaptor plate was too tight considering
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| the service-related | | #SB-106. This bulletin recommends that the anti-rotation2) Service Bulletin |
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| wear that had occurred to the rest of the keyway. Maine Yankee engineers | | for possible wear which could result in failure and keys be inspected |
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| specified
| | given to replacing the keys at the earliest convenient that consideration be |
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| that new larger keyways should be cut in the adaptor plate to prevent the key from breaking when the valve is actuated.
| | keys, which have been supplied by Velan for the time. The replacement |
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| The licensee repaired all the affected valves and then tested the valves to ensure that they operated satisfactorily.
| | past 24 years, are made of |
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| Before testing MOYs at Prairie Island this past winter, an inspection
| | material meeting American Iron and Steel Institute |
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| of Velan globe valves also discovered
| | opposed to 440C stainless steel (440C SS). AISI (AISI) 4140 alloy steel, as |
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| anti-rotation
| | 4140 is significantly tougher |
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| key failures (2 broken keys found in 16 valves) in similar systems. Because of the location of the break on the anti-rotation
| | than 440C SS. According to Velan, the material was |
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| key, and the length of the key and key slot, Northern States Power Company, the licensee, believed that the broken anti-rotation
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| keys would still perform their intended function and that the broken piece (i.e., the short leg of the L-shaped key) would not interact with the valve stem so as to impede valve operation.
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| This is at variance with the Kewaunee event discussed above. The licensee added a step to their generic actuator replacement
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| procedure
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| to inspect, clean, debur, and lubricate
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| anti-rotation
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| devices.Discussion
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| On April 5, 1993, Velan issued the attached (Attachment
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| 2) Service Bulletin#SB-106. This bulletin recommends
| | 4140 is easier to procure and to heat treat properly. changed to 4140 because |
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| that the anti-rotation
| | this bulletin to all U.S. nuclear utilities. On Velan plans to send |
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| keys be inspected for possible wear which could result in failure and that consideration
| | between the NRC staff and Velan subsequent to the the basis of conversations |
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| be given to replacing
| | and because of the hardness of anti-rotation keys issuance of the bulletin, made |
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| the keys at the earliest convenient | | suggests that both the keys and the keyways be inspected out of 440C SS, Velan |
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| time. The replacement
| | deterioration. The experience cited above indicates for damage and |
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| keys, which have been supplied by Velan for the past 24 years, are made of material meeting American Iron and Steel Institute (AISI) 4140 alloy steel, as opposed to 440C stainless | | material in anti-rotation keys can lead to failures, that the use of brittle |
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| steel (440C SS). AISI 4140 is significantly
| | may not always be impaired. although valve operation |
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| tougher than 440C SS. According
| | _ a |
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| to Velan, the material was changed to 4140 because 4140 is easier to procure and to heat treat properly.
| | IN 93-42 June 9, 1993 This information notice requires no specific action or written response. If |
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| Velan plans to send this bulletin to all U.S. nuclear utilities.
| | you have any questions about the information in this notice, please contact |
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| ===On the basis of conversations===
| | the technical contact listed below or the appropriate Office of Nuclear |
| between the NRC staff and Velan subsequent
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| to the issuance of the bulletin, and because of the hardness of anti-rotation
| | Reactor Regulation (NRR) project manager. |
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| keys made out of 440C SS, Velan suggests that both the keys and the keyways be inspected
| | Brian K. Grimes, Director |
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| for damage and deterioration.
| | Division of Operating Reactor Support |
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| The experience
| | Office of Nuclear Reactor Regulation |
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| cited above indicates
| | Technical contact: David C. Fischer, NRR |
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| that the use of brittle material in anti-rotation
| | (301) 504-2728 Attachments: (' w ) |
| | 1. Figure 1, Velan Valve and Anti-Rotation Key |
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| keys can lead to failures, although valve operation may not always be impaired._ a
| | 2. Velan Service Bulletin #SB-106 |
| | 3. List of Recently Issued NRC Information Notices |
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| IN 93-42 June 9, 1993 This information | | N- |
| | Attachment 1 IN 93-42 June 9, 1993 VELAN VALVE AND ANTI-ROTATION KEY |
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| notice requires no specific action or written response.
| | STEM, |
| | 11/X_ 5 ACME-2G-L.H. |
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| If you have any questions
| | PITCH: .200 |
| | LEAD: .200 BUSHING |
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| about the information
| | KEYWAY |
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| in this notice, please contact the technical
| | VALVE., |
| | BUSHING |
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| contact listed below or the appropriate
| | STEM |
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| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | Attachment 2 |
| | -_ IN 93-42 June 9, 1993 _,VEAS |
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| ===Reactor Support Office of Nuclear Reactor Regulation===
| | - SERVICE BUlll ~- I#SB-1 i |
| Technical
| |
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| contact: David C. Fischer, NRR (301) 504-2728 Attachments:
| | SUBJECT:-GLOBE VALVE STEM ANTROAIIO KEY |
| (' w )1. Figure 1, Velan Valve and Anti-Rotation
| |
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| Key 2. Velan Service Bulletin #SB-106 3. List of Recently Issued NRC Information
| | This is to advise you that an "LI shaped, globe valve stem anti- rotation key failed at Kewaunee Nuclear Plant. The valve in question |
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| Notices
| | is a 2; Motor operated globe valve originally supplied to drawing |
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| N-Attachment
| | 137.116/1. |
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| 1 IN 93-42 June 9, 1993 VELAN VALVE AND ANTI-ROTATION
| | The valves affected are those Motor Operated Globe valves requiring a |
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| KEY STEM, 1 1/X_ 5 ACME-2G-L.H.
| | key installed in mounting flange which prevents the stem from |
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| PITCH: .200 LEAD: .200 BUSHING KEYWAY VALVE., BUSHING STEM
| | rotating. Globe valves which have been supplied with torque arms are |
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| Attachment
| | not affected by this failure. |
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| 2-_ IN 93-42 June 9, 1993 _,VEAS-SERVICE BUlll ~- I#SB-1 i SUBJECT:-GLOBE
| | Based on the incident at Kewaunee Nuclear Plant we recommend that keys |
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| VALVE STEM ANTROAIIO
| | be inspected for possible wear which could result in failure. |
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| KEY This is to advise you that an "LI shaped, globe valve rotation key failed at Kewaunee Nuclear Plant. The valve is a 2; Motor operated globe valve originally
| | Consideration should also be given to replacing keys at your earliest |
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| supplied 137.116/1. | | possible convenience with new keys. These new keys are supplied in |
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| stem anti-in question to drawing The valves affected are those Motor Operated Globe valves requiring
| | material meeting AISI 4140. This material replaces the 440C grade |
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| a key installed
| | which several project drawings call up. |
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| in mounting flange which prevents the stem from rotating.
| | Replacement keys which have been supplied by us during the last 2 1/2 years have been from this new material. If these have been installed, only regular periodic verification will be required. If no inspection |
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| Globe valves which have been supplied with torque arms are not affected by this failure.Based on the incident at Kewaunee Nuclear Plant we recommend
| | and or replacements has been made, we recommend that key. be replaced. |
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| that keys be inspected
| | For additional information or replacement keys, please contact: |
| | Velan valve Corp. |
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| for possible wear which could result in failure.Consideration
| | 550 McArthur |
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| should also be given to replacing
| | Montreal, Quebec |
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| keys at your earliest possible convenience
| | H4T 1X8 Attn t Nuclear Division |
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| with new keys. These new keys are supplied in material meeting AISI 4140. This material replaces the 440C grade which several project drawings call up.Replacement
| | Phone: 514-748-7743 Pax s 514-342-2311 Nilaeon |
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| keys which have been supplied by us during the last 2 1/2 years have been from this new material.
| | Ic - esident, Quality Assurance Manager, nuclear Division |
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| If these have been installed, only regular periodic verification
| | - p--v.. |
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| will be required.
| | pa--. |
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| ===If no inspection===
| | 1 of 1 I |
| and or replacements
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| has been made, we recommend
| | 0 |
| | I'Tiril 5f 1993 By |
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| that key. be replaced.For additional
| | l |
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| information
| | My: .I. Francois |
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| or replacement
| | 3.1. Francois Ilew 0o 1".. 1 of 1 I |
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| keys, please contact: Velan valve Corp.550 McArthur Montreal, Quebec H4T 1X8 Attn t Nuclear Division Phone: 514-748-7743 Pax s 514-342-2311 Ic -esident, Quality Assurance Nilaeon Manager, nuclear Division-pa--. I p--v..My: 3.1. Francois 0 1 of 1 I'Tiril 5f 1993 By l .I. Francois Ilew 0o 1"..1 of 1 I
| | '-I |
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| '-I Attachment | | Attachment 3 IN 93-42 June 9, 1993 Page l'of I |
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| 3 IN 93-42 June 9, 1993 Page l'of I LIST OF RECENTLY ISSUED NRC INFORMATION
| | LIST OF RECENTLY ISSUED |
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| NOTICES Information | | NRC INFORMATION NOTICES |
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| Date of Notice No. Subject Issuance Issued to 93-41 93-40 93-39 93-38 93-37 93-36 93-35 93-34, Supp. 1 One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Barrier Systems Fire Endurance | | Information Date of |
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| Test Results for Thermal Ceramics FP-60 Fire Barrier Material Radiation
| | Notice No. Subject Issuance Issued to |
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| Beams from Power Reactor Biolog-ical Shields Inadequate
| | 93-41 One Hour Fire Endurance 05/28/93 All holders of OLs or CPs |
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| Testing of Engineered
| | Test Results for Thermal for nuclear power reactors. |
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| Safety Features Actuation System Eyebolts with Indeter-minate Properties
| | Ceramics Kaowool, 3M |
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| In-stalled in Limitorque
| | Company FS-195 and |
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| Valve Operator Housing Covers Notifications, Reports, and Records of Misadmin-istrations
| | 3M Company Interam E-50 |
| | Barrier Systems |
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| Insights from Common-Cause Failure Events Potential
| | 93-40 Fire Endurance Test 05/26/93 All holders of OLs or CPs |
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| for Loss of Emergency | | Results for Thermal for nuclear power reactors. |
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| Cooling Function Due to A Combination
| | Ceramics FP-60 Fire |
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| of Operational
| | Barrier Material |
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| |
|
| and Post-Loca Debris in Contain-ment 05/28/93 05/26/93 05/25/93 05/24/93 05/19/93 05/07/93 05/12/93 05/06/93 All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All holders of OLs or CPs for nuclear power reactors.All U.S. Nuclear Regulatory
| | 93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs |
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| |
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| Commission
| | Power Reactor Biolog- for nuclear power reactors. |
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| medical licensees.
| | ical Shields |
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| |
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| All holders of OLs or CPs for nuclear power plants (NPPs).All holders of OLs or CPs for nuclear power reactors.OL = Operating
| | 93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs |
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| |
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| License CP = Construction
| | Engineered Safety for nuclear power reactors. |
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| |
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| Permit
| | Features Actuation |
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| |
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| IN 93-42 June 9, 1993 This information
| | System |
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| |
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| notice requires no specific action or written response.
| | 93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs |
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| |
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| If you have any questions
| | minate Properties In- for nuclear power reactors. |
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| |
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| about the information
| | stalled in Limitorque |
|
| |
|
| in this notice, please contact the technical
| | Valve Operator Housing |
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| |
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| contact listed below or the appropriate
| | Covers |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Original signed by Brian K. Grimes Brian K. Grimes, Director Division of Operating
| | 93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | and Records of Misadmin- Commission medical |
| Technical
| |
|
| |
|
| contact: David C. Fischer, NRR (301) 504-2728 Attachments:
| | istrations licensees. |
| 1. Figure 1, Velan Valve and Anti-Rotation
| |
|
| |
|
| Key 2. Velan Service Bulletin #SB-106 3. List of Recently Issued NRC Information
| | 93-35 Insights from Common- 05/12/93 All holders of OLs or CPs |
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| |
|
| Notices*See previous concurrence
| | Cause Failure Events for nuclear power plants |
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| |
|
| sheet*EMEB:DE:NRR
| | (NPPs). |
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| |
|
| DCFischer 4/15/93*C/EMCB:DE:NRR
| | 93-34, Potential for Loss of 05/06/93 All holders of OLs or CPs |
|
| |
|
| ===JRStrosnider===
| | Supp. 1 Emergency Cooling for nuclear power reactors. |
| 4/20/93*OGCB:DORS:NRR
| |
|
| |
|
| RJKiessel 05/03/93*SC/EMEB:DE:NRR
| | Function Due to A |
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| |
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| EJSullivan
| | Combination of |
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| |
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| 4/16/93*C/RVIB:DRIL
| | Operational and Post- Loca Debris in Contain- ment |
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| |
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| LJNorrholm
| | OL = Operating License |
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| |
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| 4/20/93*C/OGCB:DORS:NRR
| | CP = Construction Permit |
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| |
|
| GHMarcus 05/12/93*RPB:ADM TechEd 4/15/93*C/EMEB:DE:NRR
| | IN 93-42 June 9, 1993 This information notice requires no specific action or written response. If |
|
| |
|
| JANorberg 4/19/93*D/DE:NRR JERichardson
| | you have any questions about the information in this notice, please contact |
|
| |
|
| 4/23/93 I0*DRS:RIII GCWright 4/21J.3 II /93 DOCUMENT NAME: 93-42.IN
| | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| IN 93-XX April 22, 1993 Even though a broken anti-rotation
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| key does not always impair valve operation, it is a concern to the NRC that anti-rotation
| | Original signed by |
|
| |
|
| keys made of such brittle material (440C SS) are used in safety-related
| | Brian K. Grimes |
|
| |
|
| valves.This information
| | Brian K. Grimes, Director |
|
| |
|
| notice requires no specific action or written response.
| | Division of Operating Reactor Support |
|
| |
|
| If you have any questions
| | Office of Nuclear Reactor Regulation |
|
| |
|
| about the information
| | Technical contact: David C. Fischer, NRR |
|
| |
|
| in this notice, please contact the technical
| | (301) 504-2728 Attachments: |
| | 1. Figure 1, Velan Valve and Anti-Rotation Key |
|
| |
|
| contact listed below or the appropriate
| | 2. Velan Service Bulletin #SB-106 |
| | 3. List of Recently Issued NRC Information Notices |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | *See previous concurrence sheet |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | *EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR |
| Technical
| |
|
| |
|
| contact: David C. Fischer, NRR (301) 504-2728 Attachments:
| | DCFischer EJSullivan TechEd JANorberg |
| 1. Figure 1, Velan Valve and Anti-Rotation
| |
|
| |
|
| Key 2. Velan Service Bulletin #SB-106 3. List of Recently Issued NRC Information
| | 4/15/93 4/16/93 4/15/93 4/19/93 I0 |
| | *C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR |
|
| |
|
| Notices Document Name:*See previous concurrence
| | JRStrosnider LJNorrholm GCWright JERichardson |
|
| |
|
| sheet*EMEB:DE:NRR
| | 4/20/93 4/20/93 4/21J.3 4/23/93 |
| | *OGCB:DORS:NRR *C/OGCB:DORS:NRR |
|
| |
|
| DCFischer 4/15/93*SC/EMEB:DE:NRR
| | RJKiessel GHMarcus |
|
| |
|
| EJSullivan
| | 05/03/93 05/12/93 II /93 DOCUMENT NAME: 93-42.IN |
|
| |
|
| 4/16/93*RPB:ADM TechEd 4/15/93*C/EMEB:DE:NRR
| | IN 93-XX |
|
| |
|
| JANorberg 4/19/93*C/EMCB:DE:NRR
| | April 22, 1993 Even though a broken anti-rotation key does not always impair valve operation, it is a concern to the NRC that anti-rotation keys made of such brittle |
|
| |
|
| ===JRStrosnider===
| | material (440C SS) are used in safety-related valves. |
| 4/20/93*C/RVIB:DRIL
| |
|
| |
|
| LJNorrholm
| | This information notice requires no specific action or written response. If |
|
| |
|
| 4/20/93*DRS:RIII GCWright 4/21/93*D/DE:NRR JERichardson
| | you have any questions about the information in this notice, please contact |
|
| |
|
| 4/23/93 OGCB:DORS:NRR
| | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| RJKiessel/ /93 C/OGCB:DORS:NRR
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| ===GHMarcusHkiM===
| | Brian K. Grimes, Director |
| f /taL/93 D/DORS:NRR
| |
|
| |
|
| r BKGrimes -/ /93 u
| | Division of Operating Reactor Support |
|
| |
|
| IN 93-XX April 22, 1993 Even though a broken anti-rotation
| | Office of Nuclear Reactor Regulation |
|
| |
|
| key does not always impair valve operation, it is a concern to the NRC that anti-rotation
| | Technical contact: David C. Fischer, NRR |
|
| |
|
| keys 'made of such brittle material (440C SS) are used in so many safety-related
| | (301) 504-2728 Attachments: |
| | 1. Figure 1, Velan Valve and Anti-Rotation Key |
|
| |
|
| valves.This information
| | 2. Velan Service Bulletin #SB-106 |
| | 3. List of Recently Issued NRC Information Notices |
|
| |
|
| notice requires no specific action or written response.
| | Document Name: |
| | *See previous concurrence sheet |
|
| |
|
| If you have any questions
| | *EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR |
|
| |
|
| about the information
| | DCFischer EJSullivan TechEd JANorberg |
|
| |
|
| in this notice, please contact the technical
| | 4/15/93 4/16/93 4/15/93 4/19/93 |
| | *C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR |
|
| |
|
| contact listed below or the appropriate
| | JRStrosnider LJNorrholm GCWright JERichardson |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | 4/20/93 4/20/93 4/21/93 4/23/93 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR r |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | RJKiessel GHMarcusHkiM BKGrimes - |
| Technical
| | / /93 f /taL/93 / /93 u |
|
| |
|
| contact: David C. Fischer, NRR (301) 504-2728 Attachments:
| | IN 93-XX |
| 1. Figure 1, Velan Valve and Anti-Rotation
| |
|
| |
|
| Key 2. Velan Service Bulletin #SB-106 3. List of Recently Issued NRC Information
| | April 22, 1993 Even though a broken anti-rotation key does not always impair valve operation, it is a concern to the NRC that anti-rotation keys 'made of such brittle |
|
| |
|
| Notices Document Name:*See previous concurrence
| | material (440C SS) are used in so many safety-related valves. |
|
| |
|
| sheet*EMEB:DE:NRR
| | This information notice requires no specific action or written response. If |
|
| |
|
| DCFischer 4/15/93*SC/EMEB:DE:NRR
| | you have any questions about the information in this notice, please contact |
|
| |
|
| EJSullivan
| | the technical contact listed below or the appropriate Office of Nuclear |
|
| |
|
| 4/16/93*RPB:ADM TechEd 4/15/93*C/EMEB:DE:NRR
| | Reactor Regulation (NRR) project manager. |
|
| |
|
| JANorberg 4/19/93*C/EMCB:DE:NRR
| | Brian K. Grimes, Director |
|
| |
|
| ===JRStrosnider===
| | Division of Operating Reactor Support |
| 4/20/93*C/RVIB:DRIL
| |
|
| |
|
| LJNorrholm
| | Office of Nuclear Reactor Regulation |
|
| |
|
| 4/20/93*DRS:RIII GCWright 4/21/93*D/DE:NRR JERichardson
| | Technical contact: David C. Fischer, NRR |
|
| |
|
| 4/23/93 OGCB:DORS:NRR
| | (301) 504-2728 Attachments: |
| | 1. Figure 1, Velan Valve and Anti-Rotation Key |
|
| |
|
| RJKiessel/ /93 C/OGCB:DORS:NRR
| | 2. Velan Service Bulletin #SB-106 |
| | 3. List of Recently Issued NRC Information Notices |
|
| |
|
| GHMarcus/ /93 D/DORS:NRR
| | Document Name: |
| | *See previous concurrence sheet |
|
| |
|
| BKGrimes/ /93
| | *EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR |
| 114r IN 93-XX-Paige3, 1993 hardness of anti-rotation
| |
|
| |
|
| keys made out of 440C SS, Velan suggests that both the keys and the keyways be inspected
| | DCFischer EJSullivan TechEd JANorberg |
|
| |
|
| for damage and deterioration.
| | 4/15/93 4/16/93 4/15/93 4/19/93 |
| | *C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR |
|
| |
|
| Even though a broken anti-rotation
| | JRStrosnider LJNorrholm GCWright JERichardson |
|
| |
|
| key does not always impair valve operation, it is a concern to the NRC that anti-rotation
| | 4/20/93 4/20/93 4/21/93 4/23/93 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR |
|
| |
|
| keys made of such brittle material (440C SS) are used in so many safety-related
| | ===RJKiessel GHMarcus BKGrimes=== |
| | / /93 / /93 / /93 |
|
| |
|
| valves.This information
| | IN 93-XX |
|
| |
|
| notice requires no specific action or written response.
| | 114r -Paige3, 1993 hardness of anti-rotation keys made out of 440C SS, Velan suggests that both |
|
| |
|
| If you have any questions
| | the keys and the keyways be inspected for damage and deterioration. |
|
| |
|
| about the information
| | Even though a broken anti-rotation key does not always impair valve operation, it is a concern to the NRC that anti-rotation keys made of such brittle |
|
| |
|
| in this notice, please contact the technical | | material (440C SS) are used in so many safety-related valves. |
|
| |
|
| contact listed below or the appropriate
| | This information notice requires no specific action or written response. If |
|
| |
|
| Office of Nuclear Reactor Regulation (NRR) project manager.Brian K. Grimes, Director Division of Operating
| | you have any questions about the information in this notice, please contact |
|
| |
|
| ===Reactor Support Office of Nuclear Reactor Regulation===
| | the technical contact listed below or the appropriate Office of Nuclear |
| Technical
| |
|
| |
|
| contact: David C. Fischer, NRR (301) 504-2728 Attachments:
| | Reactor Regulation (NRR) project manager. |
| 1. Figure 1, Velan Valve and Anti-Rotation
| |
|
| |
|
| Key 2. Velan Service Bulletin #SB-106 3. List of Recently Issued NRC Information
| | Brian K. Grimes, Director |
|
| |
|
| Notices Document Name:*See previous concurrence
| | Division of Operating Reactor Support |
|
| |
|
| sheet*EMEB:DE:NRR
| | Office of Nuclear Reactor Regulation |
|
| |
|
| DCFischer 4/15/93*SC/EMEB:DE:NRR
| | Technical contact: David C. Fischer, NRR |
|
| |
|
| EJSullivan
| | (301) 504-2728 Attachments: |
| | 1. Figure 1, Velan Valve and Anti-Rotation Key |
|
| |
|
| 4/16/93*RPB:ADM TechEd 4/15/93*C/EMEB:DE:NRR
| | 2. Velan Service Bulletin #SB-106 |
| | 3. List of Recently Issued NRC Information Notices |
|
| |
|
| JANorberg 4/19/93*C/EMCB:DE:NRR
| | Document Name: |
| | *See previous concurrence sheet |
|
| |
|
| ===JRStrosnider===
| | *EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR |
| 4/20/93*C/RVIB:DRIL
| |
|
| |
|
| LJNorrholm
| | DCFischer EJSullivan TechEd JANorberg |
|
| |
|
| 4/20/93*DRS:RIII GCWright 4/21/93*D/DE:NRR JERichardson | | 4/15/93 4/16/93 4/15/93 4/19/93 |
| | *C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR |
|
| |
|
| 4/23/93 OGCB:DORS:NRR4, RJKiessel g/gJ/93 MQ<C/OGCB:DORS:NRR
| | JRStrosnider LJNorrholm GCWright JERichardson |
|
| |
|
| GHMarcus/ /93 D/DORS:NRR
| | 4/20/93 4/20/93 4/21/93 4/23/93 OGCB:DORS:NRR4, C/OGCB:DORS:NRR D/DORS:NRR |
|
| |
|
| BKGrimes/ /93 Document Name:G:\FISCHER\VELAN.IN | | ===RJKiessel GHMarcus BKGrimes=== |
| | g/gJ/93 MQ< / /93 / /93 |
|
| |
|
| EMEB:DE:NRR
| | Document Name:G:\FISCHER\VELAN.IN CDoo t1-1 1I.c"641 Ott FRv |
|
| |
|
| 8 :NRR DCFischer | | EMEB:DE:NRR 8 :NRR RPB:ADM C:& rgRR |
|
| |
|
| EJSe 1yn 9 /ir/93 4/l /CDoo t1-1 1I.c"641 Ott FRv RPB:ADM TechEd V /f/93 lee OmIL A/ /3 IDRS :R I I I'346s GCWright 4 /'i /93 C:& rgRR D: DE: NRR JERichard | | ===DCFischer EJSe 1yn TechEd=== |
| | 9/ir/93 4/l / V/f/93 IDRS :R III'346s D: DE: NRR |
|
| |
|
| n t/N~3/93 OGCB:DORS:NRR | | lee OmIL GCWright JERichard n |
|
| |
|
| RJKiessel/ /93 C/OGCB:DORS:NRR
| | A/ /3 4 /'i/93 t/N~3/93 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR |
|
| |
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| GHMarcus/ /93 D/DORS:NRR | | RJKiessel GHMarcus BKGrimes |
|
| |
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| BKGrimes/ /93}}
| | / /93 / /93 / /93}} |
|
| |
|
| {{Information notice-Nav}} | | {{Information notice-Nav}} |
Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by YelanML031070501 |
Person / Time |
---|
Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant ![Entergy icon.png](/w/images/7/79/Entergy_icon.png) |
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Issue date: |
06/09/1993 |
---|
From: |
Grimes B Office of Nuclear Reactor Regulation |
---|
To: |
|
---|
References |
---|
IN-93-042, NUDOCS 9306030147 |
Download: ML031070501 (12) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2010-12, Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notic2012-08-17017 August 2012 Intervenors' Fifth Motion to Amend And/Or Supplement Proposed Contention No. 5 (Shield Building Cracking). Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
"-
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555 June 9, 1993 NRC INFORMATION NOTICE 93-42: FAILURE OF ANTI-ROTATION KEYS IN MOTOR-OPERATED
VALVES MANUFACTURED BY VELAN
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information of
notice to alert addressees to potential problems resulting from the failure
anti-rotation keys in motor-operated globe valves manufactured by Velan forValve
Corporation. It is expected that recipients will review the information to
applicability to their facilities and consider actions, as appropriate, avoid similar problems. However, suggestions contained in this information or
notice do not constitute NRC requirements; therefore, no specific action
written response is required.
Description of Circumstances
On March 28, 1993, Wisconsin Public Service Corporation, the licensee for
Kewaunee Nuclear Power Plant, reported that during motor-operated valve (MOV)
dynamic testing on March 27, 1993, one of two redundant safety injection
recirculation valves to the refueling water storage tank failed to close
completely. Investigation revealed that the anti-rotation device, an L-shaped
key between the valve stem and the yoke bushing (Attachment 1), had broken.
The shorter part of the broken L-shaped key had apparently worked its way The
toward the valve stem and had jammed the valve stem, preventing closing.
valve that failed was a 2-inch bonnetless globe valve manufactured by Velan and
Valve Corp. The licensee inspected all nine similar motor-operated valves and
found that six had broken anti-rotation keys. The inspections were visual can
did not require disassembly of the motor-operated valve. Failures usually
be observed on normally closed valves, since the broken long leg of the
L-shaped key slides down partially and becomes visible below the yoke bushing.
According to the licensee, the keys failed in a brittle manner. The fractures
began on either side of the key at the sharp radius of the inside corner of
the L-shaped key and propagated into the body of the key. Machining of the
sharp inside corner of the L-shaped key may have contributed to the failure of
the anti-rotation keys by producing high stresses in the corner of the keys.
It is likely that the rotational action of the valve stem impacted on both
sides of the key, exceeding the impact strength of the material at the sharp
radius of the key.
9306030147 POR SIE Wr;c-c 913o0&i 93o0wt
41 'C1301q3 in le- // A
IN 93-42 June 9, 1993 In 1990, at the Maine Yankee Atomic Power Station, anti-rotation
4-inch MOVs manufactured by Velan failed. Maine Yankee keys in
the licensee, discovered that spare keys supplied by Atomic Power Company, valves were not of the proper hardness; they were RockwellVelan for several of the
harder Rockwell C-59 as originally specified. Valves C-20 instead of the
wrong anti-rotation keys installed were disassembled, that may have had the
replaced the Rockwell C-20 keys with keys made of the and the licensee
non-conforming keys that were removed showed signs correct material. The
During post-maintenance testing, several of the new of significant wear.
the corner of the 'L" shape. This happened because (hardened) keys broke at
the
adaptor plate was too tight considering the service-related keyway in the valve
occurred to the rest of the keyway. Maine Yankee engineers wear that had
larger keyways should be cut in the adaptor plate to specified that new
breaking when the valve is actuated. The licensee prevent the key from
valves and then tested the valves to ensure that they repaired all the affected
operated satisfactorily.
Before testing MOYs at Prairie Island this past winter, globe valves also discovered anti-rotation key failures an inspection of Velan
in 16 valves) in similar systems. Because of the (2 broken keys found
location of the break on the
anti-rotation key, and the length of the key and key
Power Company, the licensee, believed that the broken slot, Northern States
still perform their intended function and that the anti-rotation keys would
short leg of the L-shaped key) would not interact broken piece (i.e., the
impede valve operation. This is at variance with with the valve stem so as to
above. The licensee added a step to their generic the Kewaunee event discussed
procedure to inspect, clean, debur, and lubricate actuator replacement
anti-rotation devices.
Discussion
On April 5, 1993, Velan issued the attached (Attachment
- SB-106. This bulletin recommends that the anti-rotation2) Service Bulletin
for possible wear which could result in failure and keys be inspected
given to replacing the keys at the earliest convenient that consideration be
keys, which have been supplied by Velan for the time. The replacement
past 24 years, are made of
material meeting American Iron and Steel Institute
opposed to 440C stainless steel (440C SS). AISI (AISI) 4140 alloy steel, as
4140 is significantly tougher
than 440C SS. According to Velan, the material was
4140 is easier to procure and to heat treat properly. changed to 4140 because
this bulletin to all U.S. nuclear utilities. On Velan plans to send
between the NRC staff and Velan subsequent to the the basis of conversations
and because of the hardness of anti-rotation keys issuance of the bulletin, made
suggests that both the keys and the keyways be inspected out of 440C SS, Velan
deterioration. The experience cited above indicates for damage and
material in anti-rotation keys can lead to failures, that the use of brittle
may not always be impaired. although valve operation
_ a
IN 93-42 June 9, 1993 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: David C. Fischer, NRR
(301) 504-2728 Attachments: (' w )
1. Figure 1, Velan Valve and Anti-Rotation Key
2. Velan Service Bulletin #SB-106
3. List of Recently Issued NRC Information Notices
N-
Attachment 1 IN 93-42 June 9, 1993 VELAN VALVE AND ANTI-ROTATION KEY
STEM,
11/X_ 5 ACME-2G-L.H.
PITCH: .200
LEAD: .200 BUSHING
KEYWAY
VALVE.,
BUSHING
STEM
Attachment 2
-_ IN 93-42 June 9, 1993 _,VEAS
- SERVICE BUlll ~- I#SB-1 i
SUBJECT:-GLOBE VALVE STEM ANTROAIIO KEY
This is to advise you that an "LI shaped, globe valve stem anti- rotation key failed at Kewaunee Nuclear Plant. The valve in question
is a 2; Motor operated globe valve originally supplied to drawing
137.116/1.
The valves affected are those Motor Operated Globe valves requiring a
key installed in mounting flange which prevents the stem from
rotating. Globe valves which have been supplied with torque arms are
not affected by this failure.
Based on the incident at Kewaunee Nuclear Plant we recommend that keys
be inspected for possible wear which could result in failure.
Consideration should also be given to replacing keys at your earliest
possible convenience with new keys. These new keys are supplied in
material meeting AISI 4140. This material replaces the 440C grade
which several project drawings call up.
Replacement keys which have been supplied by us during the last 2 1/2 years have been from this new material. If these have been installed, only regular periodic verification will be required. If no inspection
and or replacements has been made, we recommend that key. be replaced.
For additional information or replacement keys, please contact:
Velan valve Corp.
550 McArthur
Montreal, Quebec
H4T 1X8 Attn t Nuclear Division
Phone: 514-748-7743 Pax s 514-342-2311 Nilaeon
Ic - esident, Quality Assurance Manager, nuclear Division
- p--v..
pa--.
1 of 1 I
0
I'Tiril 5f 1993 By
l
My: .I. Francois
3.1. Francois Ilew 0o 1".. 1 of 1 I
'-I
Attachment 3 IN 93-42 June 9, 1993 Page l'of I
LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
93-41 One Hour Fire Endurance 05/28/93 All holders of OLs or CPs
Test Results for Thermal for nuclear power reactors.
Ceramics Kaowool, 3M
Company FS-195 and
3M Company Interam E-50
Barrier Systems
93-40 Fire Endurance Test 05/26/93 All holders of OLs or CPs
Results for Thermal for nuclear power reactors.
Ceramics FP-60 Fire
Barrier Material
93-39 Radiation Beams from 05/25/93 All holders of OLs or CPs
Power Reactor Biolog- for nuclear power reactors.
ical Shields
93-38 Inadequate Testing of 05/24/93 All holders of OLs or CPs
Engineered Safety for nuclear power reactors.
Features Actuation
System
93-37 Eyebolts with Indeter- 05/19/93 All holders of OLs or CPs
minate Properties In- for nuclear power reactors.
stalled in Limitorque
Valve Operator Housing
Covers
93-36 Notifications, Reports, 05/07/93 All U.S. Nuclear Regulatory
and Records of Misadmin- Commission medical
istrations licensees.
93-35 Insights from Common- 05/12/93 All holders of OLs or CPs
Cause Failure Events for nuclear power plants
(NPPs).
93-34, Potential for Loss of 05/06/93 All holders of OLs or CPs
Supp. 1 Emergency Cooling for nuclear power reactors.
Function Due to A
Combination of
Operational and Post- Loca Debris in Contain- ment
OL = Operating License
CP = Construction Permit
IN 93-42 June 9, 1993 This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Original signed by
Brian K. Grimes
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: David C. Fischer, NRR
(301) 504-2728 Attachments:
1. Figure 1, Velan Valve and Anti-Rotation Key
2. Velan Service Bulletin #SB-106
3. List of Recently Issued NRC Information Notices
- See previous concurrence sheet
- EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR
DCFischer EJSullivan TechEd JANorberg
4/15/93 4/16/93 4/15/93 4/19/93 I0
- C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR
JRStrosnider LJNorrholm GCWright JERichardson
4/20/93 4/20/93 4/21J.3 4/23/93
- OGCB:DORS:NRR *C/OGCB:DORS:NRR
RJKiessel GHMarcus
05/03/93 05/12/93 II /93 DOCUMENT NAME: 93-42.IN
IN 93-XX
April 22, 1993 Even though a broken anti-rotation key does not always impair valve operation, it is a concern to the NRC that anti-rotation keys made of such brittle
material (440C SS) are used in safety-related valves.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: David C. Fischer, NRR
(301) 504-2728 Attachments:
1. Figure 1, Velan Valve and Anti-Rotation Key
2. Velan Service Bulletin #SB-106
3. List of Recently Issued NRC Information Notices
Document Name:
- See previous concurrence sheet
- EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR
DCFischer EJSullivan TechEd JANorberg
4/15/93 4/16/93 4/15/93 4/19/93
- C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR
JRStrosnider LJNorrholm GCWright JERichardson
4/20/93 4/20/93 4/21/93 4/23/93 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR r
RJKiessel GHMarcusHkiM BKGrimes -
/ /93 f /taL/93 / /93 u
IN 93-XX
April 22, 1993 Even though a broken anti-rotation key does not always impair valve operation, it is a concern to the NRC that anti-rotation keys 'made of such brittle
material (440C SS) are used in so many safety-related valves.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: David C. Fischer, NRR
(301) 504-2728 Attachments:
1. Figure 1, Velan Valve and Anti-Rotation Key
2. Velan Service Bulletin #SB-106
3. List of Recently Issued NRC Information Notices
Document Name:
- See previous concurrence sheet
- EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR
DCFischer EJSullivan TechEd JANorberg
4/15/93 4/16/93 4/15/93 4/19/93
- C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR
JRStrosnider LJNorrholm GCWright JERichardson
4/20/93 4/20/93 4/21/93 4/23/93 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR
RJKiessel GHMarcus BKGrimes
/ /93 / /93 / /93
IN 93-XX
114r -Paige3, 1993 hardness of anti-rotation keys made out of 440C SS, Velan suggests that both
the keys and the keyways be inspected for damage and deterioration.
Even though a broken anti-rotation key does not always impair valve operation, it is a concern to the NRC that anti-rotation keys made of such brittle
material (440C SS) are used in so many safety-related valves.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
the technical contact listed below or the appropriate Office of Nuclear
Reactor Regulation (NRR) project manager.
Brian K. Grimes, Director
Division of Operating Reactor Support
Office of Nuclear Reactor Regulation
Technical contact: David C. Fischer, NRR
(301) 504-2728 Attachments:
1. Figure 1, Velan Valve and Anti-Rotation Key
2. Velan Service Bulletin #SB-106
3. List of Recently Issued NRC Information Notices
Document Name:
- See previous concurrence sheet
- EMEB:DE:NRR *SC/EMEB:DE:NRR *RPB:ADM *C/EMEB:DE:NRR
DCFischer EJSullivan TechEd JANorberg
4/15/93 4/16/93 4/15/93 4/19/93
- C/EMCB:DE:NRR *C/RVIB:DRIL *DRS:RIII *D/DE:NRR
JRStrosnider LJNorrholm GCWright JERichardson
4/20/93 4/20/93 4/21/93 4/23/93 OGCB:DORS:NRR4, C/OGCB:DORS:NRR D/DORS:NRR
RJKiessel GHMarcus BKGrimes
g/gJ/93 MQ< / /93 / /93
Document Name:G:\FISCHER\VELAN.IN CDoo t1-1 1I.c"641 Ott FRv
EMEB:DE:NRR 8 :NRR RPB:ADM C:& rgRR
DCFischer EJSe 1yn TechEd
9/ir/93 4/l / V/f/93 IDRS :R III'346s D: DE: NRR
lee OmIL GCWright JERichard n
A/ /3 4 /'i/93 t/N~3/93 OGCB:DORS:NRR C/OGCB:DORS:NRR D/DORS:NRR
RJKiessel GHMarcus BKGrimes
/ /93 / /93 / /93
|
---|
|
list | - Information Notice 1993-01, Accuracy of Motor-Operated Valve Diagnostic Equipment Manufactured by Liberty Technologies (4 January 1993)
- Information Notice 1993-02, Malfunction of a Pressurizer Code Safety Valve (4 January 1993, Topic: Loop seal)
- Information Notice 1993-04, Investigation and Reporting of Misadministrations by the Radiation Safety Officer (7 January 1993, Topic: Uranium Hexafluoride, Overexposure)
- Information Notice 1993-05, Locking of Radiography Exposure Devices (14 January 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-06, Potential Bypass Leakage Paths Around Filters Installed in Ventilation Systems (22 January 1993)
- Information Notice 1993-07, Classification of Transportation Emergencies (1 February 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-08, Failure of Residual Heat Removal Pump Bearings Due to High Thrust Loading (1 February 1993, Topic: Probabilistic Risk Assessment)
- Information Notice 1993-09, Failure of Undervoltage Trip Attachment on Westinghouse Model DB-50 Reactor Trip Breaker (2 February 1993)
- Information Notice 1993-10, Dose Calibrator Quality Control (2 February 1993, Topic: Uranium Hexafluoride)
- Information Notice 1993-11, Single Failure Vulnerability of Engineered Safety Features Actuation Systems (4 February 1993)
- Information Notice 1993-12, Off-Gassing in Auxiliary Feedwater System Raw Water Sources (11 February 1993)
- Information Notice 1993-13, Undetected Modification of Flow Characteristics in High Pressure Safety Injection System (16 February 1993)
- Information Notice 1993-14, Clarification of 10 CFR 40.22, Small Quantities of Source Material (18 February 1993)
- Information Notice 1993-15, Failure to Verify the Continuity of Shunt Trip Attachment Contacts in Manual Safety Injection and Reactor Trip Switches (18 February 1993)
- Information Notice 1993-16, Failures of Not-Locking Devices in Check Valves (19 February 1993, Topic: Anchor Darling, Flow Induced Vibration)
- Information Notice 1993-17, Safety Systems Response to Loss of Coolant and Loss of Offsite Power (25 March 1994, Topic: Fire Barrier, Backfit)
- Information Notice 1993-18, Portable Moisture-Density Gauge User Responsibilities During Field Operations (10 March 1993, Topic: Moisture Density Gauge, Moisture-Density Gauge, Stolen)
- Information Notice 1993-19, Slab Hopper Bulging (17 March 1993, Topic: Hydrostatic)
- Information Notice 1993-20, Thermal Fatigue Cracking of Feedwater Piping to Steam Generators (24 March 1993)
- Information Notice 1993-21, Summary of NRC Staff Observations Compiled During Engineering Audits or Inspections of Licensee Erosion/Corrosion Programs (25 March 1993, Topic: Weld Overlay, Thermal fatigue)
- Information Notice 1993-22, Tripping of Klockner-Moeller Molded-Case Circuit Breakers Due to Support Lever Failure (26 March 1993)
- Information Notice 1993-23, Weschler Instruments Model 252 Switchboard Meters (31 March 1993)
- Information Notice 1993-24, Distribution of Revision 7 of NUREG-1021, Operation Licensing Examiner Standards (31 March 1993, Topic: Job Performance Measure)
- Information Notice 1993-25, Electrical Penetration Assembly Degradation (1 April 1993)
- Information Notice 1993-26, Grease Soldification Causes Molded-Case Circuit Breaker Failure to Close (31 January 1994)
- Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization (8 April 1993, Topic: Reactor Vessel Water Level)
- Information Notice 1993-28, Failure to Consider Loss of DC Bus in the Emergency Core Cooling System Evaluation May Lead to Nonconservative Analysis (9 April 1993, Topic: Fuel cladding)
- Information Notice 1993-29, Problems with the Use of Unshielded Test Leads in Reactor Protection System Circuitry (12 April 1993)
- Information Notice 1993-30, NRC Requirements for Evaluation of Wipe Test Results; Calibration of Count Rate Survey Instruments (12 April 1993)
- Information Notice 1993-31, Training of Nurses Responsible for the Care of Patients with Brachytherapy Implants (13 April 1993, Topic: Brachytherapy)
- Information Notice 1993-32, Nonconservative Inputs for Boron Dilution Events Analysis (21 April 1993, Topic: Shutdown Margin)
- Information Notice 1993-33, Potential Deficiency of Certain Class Ie Instrumental and Control Cables (28 April 1993)
- Information Notice 1993-33, Potential Deficiency of Certain Class IE Instrumental and Control Cables (28 April 1993, Topic: Brachytherapy)
- Information Notice 1993-34, Potential for Loss of Emergency Cooling Function Due to a Combination of Operational and Post-LOCA Debris in Containment (6 May 1993, Topic: Brachytherapy)
- Information Notice 1993-35, Insights from Common-Cause Failure Events (12 May 1993, Topic: Brachytherapy)
- Information Notice 1993-36, Notifications, Reports, and Records of Misadministrations (7 May 1993, Topic: Brachytherapy)
- Information Notice 1993-37, Eyebolts with Indeterminate Properties Installed in Limitorque Valve Operator Housing Covers (19 May 1993, Topic: Brachytherapy)
- Information Notice 1993-38, Inadequate Testing of Engineered Safety Features Actuation Systems (24 May 1993)
- Information Notice 1993-39, Radiation Beams From Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-39, Radiation Beams from Power Reactor Biological Shields (25 May 1993)
- Information Notice 1993-40, Fire Endurance Test Results for Thermal Ceramics FP-60 Fire Barrier Material (26 May 1993, Topic: Safe Shutdown, Fire Barrier, Fire Protection Program)
- Information Notice 1993-41, One Hour Fire Endurance Test Results for Thermal Ceramics Kaowool, 3M Company FS-195 and 3M Company Interam E-50 Fire Barrier Systems (28 May 1993, Topic: Safe Shutdown, Fire Barrier)
- Information Notice 1993-42, Failure of Anti-Rotation Keys in Motor-Operated Valves Manufactured by Yelan (9 June 1993)
- Information Notice 1993-43, Use of Inappropriate Lubrication Oils in Satety-Related Applications (10 June 1993)
- Information Notice 1993-44, Operational Challenges During a Dual-Unit Transient (15 June 1993)
- Information Notice 1993-45, Degradation of Shutdown Cooling System Performance (16 June 1993)
- Information Notice 1993-46, Potential Problem with Westinghouse Rod Control System and Inadvertent Withdrawal of Single Rod Control Cluster Assembly (10 June 1993)
- Information Notice 1993-47, Unrecognized Loss of Control Room Annunciators (18 June 1993)
- Information Notice 1993-48, Failure of Turbine-Driven Main Feedwater Pump to Trip Because of Contaminated Oil (6 July 1993)
- Information Notice 1993-49, Improper Integration of Software Into Operating Practices (8 July 1993)
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