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        .                                                                                            l CITIZENS' UTILITY BOARD                                                             l
CITIZENS' UTILITY BOARD l
      -  16 N. Carroll St., Suite 300 Madison, WI 53703 + (608) 251-3322 + FAX (608) 251-7609 -
16 N. Carroll St., Suite 300 Madison, WI 53703 + (608) 251-3322 + FAX (608) 251-7609 -
EREIDOM 0F INFORMATION   i August 5, 1996                                                             ACT REQUEST Mr. Russell Powell                                                  Porn-16 .32t Branch Chief FOIA/LPDR Nuclear Regulatory Commission Nec/d 9 /M7d           l Washington, D.C.
EREIDOM 0F INFORMATION i
.        20555 Re:     Freedom of Information Act Request
ACT REQUEST August 5, 1996 Porn-16
.32t Mr. Russell Powell Branch Chief FOIA/LPDR Nec/d 9 /M7d Nuclear Regulatory Commission Washington, D.C.
20555 Re:
Freedom of Information Act Request


==Dear Mr. Powell:==
==Dear Mr. Powell:==
1 Pursuant to the Freedom of Information Act, 5 U.S.C. 522, as amended and 10 C.F.R. Part 9.41, the Wisconsin Citizens' Utility                             l Board (CUB) requests the following documents:
Pursuant to the Freedom of Information Act, 5 U.S.C.
: 1.     Please provide any and all documents that make a specific reference to the event at the Point Beach nuclear power plant,                         l Dockets 50-266 and 50-301,               involving a gaseous ignition incident during the welding of a spent fuel cask.                   This event was identified by the NRC in Preliminary Notification of Event or Unusual Occurrence PNO-III-96-033 on May 28, 1996;                                 i
522, as amended and 10 C.F.R.
: 2.     Please provide         any and     all documents that address the generation of explosive gases during any phase of operation of the VSC-24 system;
Part 9.41, the Wisconsin Citizens' Utility Board (CUB) requests the following documents:
: 3.     Please provide any and all documents that address the ignition of explosive gases during any phase of operation of the VSC-24 system.                                                                               l
1.
.                    On June 4, 1996 CUB submitted a FOIA request to the NRC requesting documents responsive to items 1-3.                     The NRC completed its response to CUB's June 4,               1996 FOIA,   identified   by the NRC as FOIA-96-244/ June 10, 1996, on July 25, 1996.                   CUB is re-submitting its FOIA request for items 1-3 to obtain documents in the agencies possession for the period of time following the date the NRC received CUB's June 4,           1996 FOIA to the date the NRC receives this FOIA request.
Please provide any and all documents that make a specific reference to the event at the Point Beach nuclear power plant, Dockets 50-266 and 50-301, involving a gaseous ignition incident during the welding of a spent fuel cask.
9610030105 960923 PDR     FOIA DUMS96-322               PDR                 ,c_A1 g
This event was identified by the NRC in Preliminary Notification of Event or Unusual Occurrence PNO-III-96-033 on May 28, 1996; i
                                                  ., war ,
2.
: 4. Please provide any and all documents that address increased neutron multiplication in the fuel in a cask because of boron precipitation from a chemical reaction among the borated water and cask materials.
Please provide any and all documents that address the generation of explosive gases during any phase of operation of the VSC-24 system; 3.
: 5. Please provide any and all documents that address the effect of.a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool on fuel cladding integrity.
Please provide any and all documents that address the ignition of explosive gases during any phase of operation of the VSC-24 system.
: 6. Please provide any and all documents that address the effect     )
* On June 4, 1996 CUB submitted a FOIA request to the NRC requesting documents responsive to items 1-3.
of a precipitate-formed by a chemical reaction of zine with       i acidic borated water from a spent fuel pool on the heat           i transfer characteristics of a VSC dry storage cask.
The NRC completed its response to CUB's June 4, 1996 FOIA, identified by the NRC as FOIA-96-244/ June 10, 1996, on July 25, 1996.
: 7. Please provide any and all documents that address the behavior of a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool under long-term exposure to neutron and gamma radiation.
CUB is re-submitting its FOIA request for items 1-3 to obtain documents in the agencies possession for the period of time following the date the NRC received CUB's June 4, 1996 FOIA to the date the NRC receives this FOIA request.
: 8. . Please provide any and all documents that address the behavior of a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool under high temperatures.
9610030105 960923 PDR FOIA DUMS96-322 PDR
: 9. Please provide any and all documents that address the effect of a zinc reaction with the acidic borated wator from a spent fuel pool on the characteristics of MSB anti-corrosion coatings.
,c_A1 g
: 10. Please provide any and all documents that address the effect of a zinc reaction with the acidic borated water from a spent     i fuel pool on the retrievability of sp6nt fuel.
., war,
: 11. Please provide any and all documents that address the effect of a zinc reaction with the acidic borated water from a spent fuel pool on the reactor coolant system.
 
For purposes of this request, please consider " documents" to include reports, studies, test results, correspondence, memoranda, meeting notes, meeting minutes, working papers, graphs, charts,         ,
4.
diagrams, notes and summaries _ of conversations and interviews,       l computer records, and any other form of written communications including internal NRC memoranda.
Please provide any and all documents that address increased neutron multiplication in the fuel in a cask because of boron precipitation from a chemical reaction among the borated water and cask materials.
Pursuant to and in compliance with 10 C.F.R.         9.41 of the .
5.
agency's regulations and 5 U.S.C. 552 governing requests for waiver   !
Please provide any and all documents that address the effect of.a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool on fuel cladding integrity.
of fees, CUB puts forth the following information.
6.
CUB was incorporated pursuant to Chapter 181, 1979, of the       !
Please provide any and all documents that address the effect
1 l
)
of a precipitate-formed by a chemical reaction of zine with i
acidic borated water from a spent fuel pool on the heat i
transfer characteristics of a VSC dry storage cask.
7.
Please provide any and all documents that address the behavior of a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool under long-term exposure to neutron and gamma radiation.
8.
. Please provide any and all documents that address the behavior of a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool under high temperatures.
9.
Please provide any and all documents that address the effect of a zinc reaction with the acidic borated wator from a spent fuel pool on the characteristics of MSB anti-corrosion coatings.
10.
Please provide any and all documents that address the effect i
of a zinc reaction with the acidic borated water from a spent fuel pool on the retrievability of sp6nt fuel.
11.
Please provide any and all documents that address the effect of a zinc reaction with the acidic borated water from a spent fuel pool on the reactor coolant system.
For purposes of this request, please consider " documents" to include reports, studies, test results, correspondence, memoranda, meeting notes, meeting minutes, working papers, graphs, charts, diagrams, notes and summaries _ of conversations and interviews, computer records, and any other form of written communications including internal NRC memoranda.
Pursuant to and in compliance with 10 C.F.R.
9.41 of the agency's regulations and 5 U.S.C. 552 governing requests for waiver of fees, CUB puts forth the following information.
CUB was incorporated pursuant to Chapter 181, 1979, of the 1 l
l
l


O Wisconsin Statutes. CUB is exempt from Federal income tax under Section 501(c)(4) of the Internal Revenue Code. CUB is also exempt from Wisconsin franchise tax.
O Wisconsin Statutes.
The restricted fund (public interest fund)     is exempt from Federal income tax under Section 501(c)(3) of the Internal Revenue Code. The fund is also exempt from Wisconsin income taxes.       The restricted fund (public interest fund) was established on February 1, 1981, and reorganized on April 28, 1986 to cocrespond to the new structure of the CUB. The fund engages in charitable, scientific, literary and educational activities on behalf of CUB.
CUB is exempt from Federal income tax under Section 501(c)(4) of the Internal Revenue Code.
CUB has 20,000 members who are residential ratepayers in Wisconsin. CUB represents the more than two million residential ratepayers in the state.       CUB's purpose continues to be the statutory purpose set forth under sec. 199.02, Wis. Stats.:
CUB is also exempt from Wisconsin franchise tax.
The restricted fund (public interest fund) is exempt from Federal income tax under Section 501(c)(3) of the Internal Revenue Code.
The fund is also exempt from Wisconsin income taxes.
The restricted fund (public interest fund) was established on February 1, 1981, and reorganized on April 28, 1986 to cocrespond to the new structure of the CUB.
The fund engages in charitable, scientific, literary and educational activities on behalf of CUB.
CUB has 20,000 members who are residential ratepayers in Wisconsin.
CUB represents the more than two million residential ratepayers in the state.
CUB's purpose continues to be the statutory purpose set forth under sec. 199.02, Wis. Stats.:
:...to promote the health, welfare and prosperity of all the citizens of this state by ensuring effective and democratic representation of individual farmers and other individual residential utility consumers before regulatory agencies, the legislature and other public bodies and by providing for consumer education on utility service costs and on benefits and methods of energy conservation.
:...to promote the health, welfare and prosperity of all the citizens of this state by ensuring effective and democratic representation of individual farmers and other individual residential utility consumers before regulatory agencies, the legislature and other public bodies and by providing for consumer education on utility service costs and on benefits and methods of energy conservation.
CUB seeks the requested information to become informed of the causes, consequences, and remedies of and for an incident which took place on May 28, 1996 involving the use of the VSC-24 storage system for spent nuclear fuel.
CUB seeks the requested information to become informed of the causes, consequences, and remedies of and for an incident which took place on May 28, 1996 involving the use of the VSC-24 storage system for spent nuclear fuel.
CUB intends to use the information to assist in its participation in any proceedings before the NRC, before state regulatory agencies, and as part of CUB's ongoing ef fort to educate the public on nuclear waste storage issues in Wisconsin.
CUB intends to use the information to assist in its participation in any proceedings before the NRC, before state regulatory agencies, and as part of CUB's ongoing ef fort to educate the public on nuclear waste storage issues in Wisconsin.
The information sought, is not, to the best of our knowledge, in the public domain.       The general public in Wisconsin has displayed great interest in nuclear waste issues and have a direct interest in NRC actions regarding the VSC-24 dry cask storage system.
The information sought, is not, to the best of our knowledge, in the public domain.
The general public in Wisconsin has displayed great interest in nuclear waste issues and have a direct interest in NRC actions regarding the VSC-24 dry cask storage system.
CUB has demonstrated its ability and commitment to inform the public on all important nuclear waste storage issues in Wisconsin.
CUB has demonstrated its ability and commitment to inform the public on all important nuclear waste storage issues in Wisconsin.
CUB provides this information free of charge through newsletters, educational pamphlets, and correspondence to its members, other residential ratepayers, legislators, and policy makers, and has neither a commercial nor a private interest in the agency records sought.
CUB provides this information free of charge through newsletters, educational pamphlets, and correspondence to its members, other residential ratepayers, legislators, and policy makers, and has neither a commercial nor a private interest in the agency records sought.
Under the amended fee waiver standard, CUB is clearly entitled to a full waiver of all search, review and duplication fees. This standard calls for such a waiver, "if disclosure of the information is in the public interest because it is likely to contribute significantly to the public understanding of the operation or
Under the amended fee waiver standard, CUB is clearly entitled to a full waiver of all search, review and duplication fees.
                                                                                      ]
This standard calls for such a waiver, "if disclosure of the information is in the public interest because it is likely to contribute significantly to the public understanding of the operation or  
]
activities of the government and is not primarily in the commercial interest of the requester." 5 U.S.C. 552 (1)(4)(A)(111).
activities of the government and is not primarily in the commercial interest of the requester." 5 U.S.C. 552 (1)(4)(A)(111).
In light of the foregoing, CUB meets this standard on its                   i face.     CUB has no commercial interest in this matter, but rather seeks this information to help the general public better understand the role of government         in regulating the nuclear industry's radioactive waste storage activities.
In light of the foregoing, CUB meets this standard on its i
For the reasons cited above, CUB's request falls squarely within the Congressional intent in enacting the Freedom of Information Act and the fee waiver provision. CUB, therefore, asks that the NRC grant a full fee waiver for this FOIA request.                       !
face.
l Thank you for your anticipated cooperation.       If you have any           l questions in regards to this request, please feel free to contact me at       your earliest convenience.       Please contact me before acquiring and sending the requested information if the fee waiver is not applied.
CUB has no commercial interest in this matter, but rather seeks this information to help the general public better understand the role of government in regulating the nuclear industry's radioactive waste storage activities.
Sincerely, l
For the reasons cited above, CUB's request falls squarely within the Congressional intent in enacting the Freedom of Information Act and the fee waiver provision. CUB, therefore, asks that the NRC grant a full fee waiver for this FOIA request.
b Dennis Dums e                                                              ,
Thank you for your anticipated cooperation.
i Research Director                                                                 l l
If you have any questions in regards to this request, please feel free to contact me at your earliest convenience.
l 4
Please contact me before acquiring and sending the requested information if the fee waiver is not applied.
Sincerely, b
e Dennis Dums i
Research Director 4
4 i
4 i
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}
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FOIA Name & Number:                       M i6       W         --
FOIA Name & Number:
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l QUESTIONS FOR WISCONSIN ELECTRIC POWER COMPANY Related to VSC-24 Cask Loading Incident A. Backcround Information, i
QUESTIONS FOR WISCONSIN ELECTRIC POWER COMPANY Related to VSC-24 Cask Loading Incident A.
: 1. Please provide a detailed description of the circumstances leading up to the event. If possible, please describe details on how the lid lifted, other sources of combustible materials present at the time, and other evolutions in progress in the vicinity of the cask decontari.' nation area.
Backcround Information, 1.
Please provide a detailed description of the circumstances leading up to the event. If possible, please describe details on how the lid lifted, other sources of combustible materials present at the time, and other evolutions in progress in the vicinity of the cask decontari.' nation area.
Had there been any problems or abnormalities during fuel movement or transfer?
Had there been any problems or abnormalities during fuel movement or transfer?
Any personnel contaminations?
Any personnel contaminations?
: 2. What were the characteristics of the spent fuel placed in the affected MSB? Were there any significant fuel characteristic differences compared to previous cask loadings?
2.
What were the characteristics of the spent fuel placed in the affected MSB? Were there any significant fuel characteristic differences compared to previous cask loadings?
(Initial enrichments, burnups, heat generation rates, etc.)
(Initial enrichments, burnups, heat generation rates, etc.)
: 3. What was the condition of the fuel assemblies placed in the MSB? Were there previously known leakers? What inspections were performed to verify the condition of the fuel before loading into the MSB?
3.
: 4. When and how much water was drained from the MSB prior to beginning welding preparations? How was the water drained out of the MSB?
What was the condition of the fuel assemblies placed in the MSB? Were there previously known leakers? What inspections were performed to verify the condition of the fuel before loading into the MSB?
: 5. Were the drain and fill ver.ts opened or closed at the time of the event?
4.
: 6. Was any cover gas used to backfill the space voided by water draw-down? If so, what type?
When and how much water was drained from the MSB prior to beginning welding preparations? How was the water drained out of the MSB?
: 7. What is the typical time between removing the cask from the pool to wold commencement? Is the 11 hours typical?
5.
11 Qtrrent Conditions / Status
Were the drain and fill ver.ts opened or closed at the time of the event?
: 1. What is being done to maintain " safe conditions?"
6.
: 2. What actions are being taken to determine the type of explosive gas that ignited?
Was any cover gas used to backfill the space voided by water draw-down? If so, what type?
7.
What is the typical time between removing the cask from the pool to wold commencement? Is the 11 hours typical?
11 Qtrrent Conditions / Status 1.
What is being done to maintain " safe conditions?"
2.
What actions are being taken to determine the type of explosive gas that ignited?
What is the current generation rate?
What is the current generation rate?
: 3. What sort of gas sampling was done before, during and after the event?
3.
: 4. What were the assumptions used to determine the 55 hour time limit for drain down....what is assumed to occupy the annulus between the MSB and the transfer cask?
What sort of gas sampling was done before, during and after the event?
4.
What were the assumptions used to determine the 55 hour time limit for drain down....what is assumed to occupy the annulus between the MSB and the transfer cask?


t t
t t
: 5. What weld method was used? Type of shield gas?
5.
: 6. What inspections / actions are planned for examining the fuel and MSB? Is there an estimate of pressure induced damage to the MSB following the event? Are there plans for sampling or monitoring the water in the MSB? What actions will be taken after the sample analyses are obtained?
What weld method was used? Type of shield gas?
C Potential Generic Issues
6.
: 1. ilas Point Beach notified others? Press release?
What inspections / actions are planned for examining the fuel and MSB? Is there an estimate of pressure induced damage to the MSB following the event? Are there plans for sampling or monitoring the water in the MSB? What actions will be taken after the sample analyses are obtained?
: 2. Plans for notifying other vendors and licensees?
C Potential Generic Issues 1.
ilas Point Beach notified others? Press release?
2.
Plans for notifying other vendors and licensees?
4 0
4 0


i CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS ELAPSED TIME (HRS: MINS)
i CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS ELAPSED TIME (HRS: MINS)
EVENT               LOAD #1           LOAD #2                     LOAD #3 Serial #           (MSB-01)         (MSB-03)                     (MSB-02)
EVENT LOAD #1 LOAD #2 LOAD #3 Serial #
Start MSB fill                               0                   0                                 0 MSB into SFP                                 1:19             4:15                               1:15.
(MSB-01)
1Aad fuel                               15:19 12 hr         19.30 12.5 hr           ~ 13.57 10.7 hr Shield lid in place                       19:04             22:45                           17:05 MSB breaks SFP surface                   23:09               26:35                           18:25 30 gal. Pump down                       23:19               26:41                           18:35 MSB out of SFP                           23:49               27:00                           19:00 Tack welds begin                         36:34               37:10                       ~29:00 Shield weld complete '                   42:19               42:30                             *
(MSB-03)
                                                                                                                                                          .{
(MSB-02)
Weld structural lid                                                                                                                 !
Start MSB fill 0
54:19 6.5 hr         65:00 12 hr
0 0
* Stnictural lid seal weld                 56:04               68:00
MSB into SFP 1:19 4:15 1:15.
* Drain MSB -                               61:19               70:00                             *
1Aad fuel 15:19 12 hr 19.30 12.5 hr
                    * - Not performe<!
~ 13.57 10.7 hr Shield lid in place 19:04 22:45 17:05 MSB breaks SFP surface 23:09 26:35 18:25 30 gal. Pump down 23:19 26:41 18:35 MSB out of SFP 23:49 27:00 19:00 Tack welds begin 36:34 37:10
MSB - Multi-Assembly Sealed Basket SFP - Spent Fuel Pool                                                                           ,
~29:00 Shield weld complete '
1 i
42:19 42:30
.{
Weld structural lid 54:19 6.5 hr 65:00 12 hr Stnictural lid seal weld 56:04 68:00 Drain MSB -
61:19 70:00
* - Not performe<!
MSB - Multi-Assembly Sealed Basket SFP - Spent Fuel Pool 1
i


i e CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS TIME AND DATE OF EVENT 9
i e CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS TIME AND DATE OF EVENT EVENT LOAD #1 LOAD #2 i
!                        EVENT                               LOAD #1         LOAD #2         i       LOAD #3 i
LOAD #3 9
4 Serial #                             (MSB-01)         (MSB-03)                 (MSB-02)                     i j-Start MSB fill                             0911 : 12/11/95     1800e : 5/20/96.         2145 : 5/26/96 l
i 4
MSB into SFP                           .1030                 2215                   2300e Load fuel                             1235-0030 : 12/12       0100-1330 : 5/21     0100e-1142 : 5/27 4
Serial #
Shield lid in place                       0415                 1645                   1450 MSB breaks SFP surface                   0820                 2035                   1610 30 gal. Pump down                       0830e                 2041                   1620e                             I MSB out of SFP                           0900                 2100                   1645 Tack welds begin                         2145                 0700e : 5/22         0245 : 5/28 Shield weld complete                     0330 : 12/13         1230 Weld structural lid                     0900-1530             2300-1100e :                   *
(MSB-01)
(                                                                         5/23 Structural lid seal weld                 1640-1715             1400e
(MSB-03)
* Drain MSB                               2145-2230             1600e-1641
(MSB-02) j-Start MSB fill 0911 : 12/11/95 1800e : 5/20/96.
* e - Time of event not recorded; estimate based on adjacent recorded events, i
2145 : 5/26/96 l
            * - Not performed                                                                                                         :
MSB into SFP
MSB - Multi-Assembly Sealed Basket SFP - Spent Fuel Pool                                                                                                     <
.1030 2215 2300e Load fuel 1235-0030 : 12/12 0100-1330 : 5/21 0100e-1142 : 5/27 4
Shield lid in place 0415 1645 1450 MSB breaks SFP surface 0820 2035 1610 30 gal. Pump down 0830e 2041 1620e MSB out of SFP 0900 2100 1645 Tack welds begin 2145 0700e : 5/22 0245 : 5/28 Shield weld complete 0330 : 12/13 1230 Weld structural lid 0900-1530 2300-1100e :
(
5/23 Structural lid seal weld 1640-1715 1400e Drain MSB 2145-2230 1600e-1641 e - Time of event not recorded; estimate based on adjacent recorded events, i
* - Not performed MSB - Multi-Assembly Sealed Basket SFP - Spent Fuel Pool


1 l
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r                                                                                            j i
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CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS
CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS
                                                                                              ]
]
l ELAPSED TIME (HRS: MINS)
ELAPSED TIME (HRS: MINS)
EVENT                 LOAD #1             LOAD #2 -     LOAD #3 Serial #             (MSB-01)             (MSB-03)       (MSB-02)
EVENT LOAD #1 LOAD #2 -
Start MSB fill                       0                       0             0 MSB into SFP                       1:19                   4:15           1:15 Load fuel                       15:19 12 hr           19:30 12.5 hr 13:57 10.7 hr Shield lid in place               19:04                 22:45           17:05 MSB breaks SFP surface           23:09                 26:35           18:25 30 gal. Pump down                 23:19                 26:41           18:35 MSB out of SFP                   23:49                 27:00           19:00 Tack welds begin                   36:34                 37:00         29:00 Shield weld complete               42:19                 42:30
LOAD #3 Serial #
* Weld structural lid           54:19 6.5 hr             65:00 12 hr
(MSB-01)
* Structural lid seal weld           56:04                 106:00'
(MSB-03)
* Drain MSB                         61:19                 70:00           *
(MSB-02)
  * - Not performed                                                                           4 MSB - Multi-Assembly Scaled Basket                                                         l SFP - Spent Fuel Pool 1 - Drained down prior to completing structural lid seal weld
Start MSB fill 0
* 19/%
0 0
MSB into SFP 1:19 4:15 1:15 Load fuel 15:19 12 hr 19:30 12.5 hr 13:57 10.7 hr Shield lid in place 19:04 22:45 17:05 MSB breaks SFP surface 23:09 26:35 18:25 30 gal. Pump down 23:19 26:41 18:35 MSB out of SFP 23:49 27:00 19:00 Tack welds begin 36:34 37:00 29:00 Shield weld complete 42:19 42:30 Weld structural lid 54:19 6.5 hr 65:00 12 hr Structural lid seal weld 56:04 106:00' Drain MSB 61:19 70:00
* - Not performed 4
MSB - Multi-Assembly Scaled Basket l
SFP - Spent Fuel Pool 1 - Drained down prior to completing structural lid seal weld 19/%


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TIME AND DATE OF EVENT EVENT                   LOAD #1           LOAD #2           LOAD #3 Serial #               (MSB-01)           (MSB-03)           (MSB-02)
TIME AND DATE OF EVENT EVENT LOAD #1 LOAD #2 LOAD #3 Serial #
Start MSB fill                   0911 : 12/11/95   1800e : 5/20/96   2145 : 5/26/96 MSB into SFP                     1030               2215               2300e Load fuel                     1235-0030 : 12/12   0100-1330 : 5/21 0100e-1142 : 5/27 Shield lid in place             0415                 1645             1450 MSB breaks SFP surface         0820               2035               1610 30 gal. hmp down               0830e               2041               1620e MSB out of SFP                 0900               2100               1645 Tack welds begin                 2145               0700e : 5/22       0245 : 5/28 Shield weld complete             0330 : 12/13       1230
(MSB-01)
* Weld structural lid             0900-1530           2300-1100e :
(MSB-03)
* 5/23                                 l Structural lid seal weld         1640-1715           0405e'   5/25
(MSB-02)
* Drain MSB                       2145-2230           1600e-1641 :
Start MSB fill 0911 : 12/11/95 1800e : 5/20/96 2145 : 5/26/96 MSB into SFP 1030 2215 2300e Load fuel 1235-0030 : 12/12 0100-1330 : 5/21 0100e-1142 : 5/27 Shield lid in place 0415 1645 1450 MSB breaks SFP surface 0820 2035 1610 30 gal. hmp down 0830e 2041 1620e MSB out of SFP 0900 2100 1645 Tack welds begin 2145 0700e : 5/22 0245 : 5/28 Shield weld complete 0330 : 12/13 1230 Weld structural lid 0900-1530 2300-1100e :
* 5/23 e - Time of event not recorded; estimate based on adjacent recorded events.
5/23 Structural lid seal weld 1640-1715 0405e' 5/25 Drain MSB 2145-2230 1600e-1641 :
        * - Not performed MSB - Multi-Assembly Sealed Basket 1 - Drained down prior to completing structural lid seal weld SFP - Spent Fuel Pool
5/23 e - Time of event not recorded; estimate based on adjacent recorded events.
* - Not performed MSB - Multi-Assembly Sealed Basket 1 - Drained down prior to completing structural lid seal weld SFP - Spent Fuel Pool


4
4
, a ISSUE STATUS AND EXIT NOTES Item 5 Determine if approoriate attention was given to the condition of systems and components associated with dry cn* evolutions. including comnatability of the dry end with soent fuel oool conditions.
, a ISSUE STATUS AND EXIT NOTES Item 5 Determine if approoriate attention was given to the condition of systems and components associated with dry cn* evolutions. including comnatability of the dry end with soent fuel oool conditions.
I examined the licensee's overview and control of the multi- assembly stoage basket (MSB) during fabrication and upon receipt. I was verified that licensee were very involved in the                 l oversight of fabrication by the contracted fabricators at the various fabrication sites. The licensee had essentially full time representation at the fabrication sites and documented their presence through the use of HOLD POINTS in the contruction documents. I observed that licensee representatives independently verified important parameters such as cleanliness, weld               l size, and material certifications. Their verifications included detailed parameters such as                 !
I examined the licensee's overview and control of the multi-assembly stoage basket (MSB) during fabrication and upon receipt. I was verified that licensee were very involved in the oversight of fabrication by the contracted fabricators at the various fabrication sites. The licensee had essentially full time representation at the fabrication sites and documented their presence through the use of HOLD POINTS in the contruction documents. I observed that licensee representatives independently verified important parameters such as cleanliness, weld size, and material certifications. Their verifications included detailed parameters such as paint thickness. I verified that on site receipt inspection also independently verified that the casks received on site had been maintained in aquality condition. I reviewed the procedures records for using the MSB and verified quality conditions had been maintained.
paint thickness. I verified that on site receipt inspection also independently verified that the casks received on site had been maintained in aquality condition. I reviewed the procedures records for using the MSB and verified quality conditions had been maintained.
I concluded that the licensee had given appropriate attention to the condition of equipment-associated with the dry cask storage evolutions.
I concluded that the licensee had given appropriate attention to the condition of equipment-associated with the dry cask storage evolutions.
The occurrence of the event makes it clear that appropriate attention was not given to the chemical compatibility of the MSB zine paint and the SFP boric acid conditions. Neither the                   j i
The occurrence of the event makes it clear that appropriate attention was not given to the chemical compatibility of the MSB zine paint and the SFP boric acid conditions. Neither the j
designer nor the licensee forsaw the potential for the chemical reaction that occurred. Several suggestions, that might have alerted the involved parties, were available. First, the paint manufacturer's specification sheet stated that the paint was not reccommended for immersion in acids. Secondly, the licensee studied the incompatibility of the paint and SFP boric acid in a study they conducted in July 1995. The study noted the potential for a zine borate pricipitate and possible coating on SFP fuel. Hydrogen generation was not addressed.. The study was a proactive effort and showed a good reflective atttude. Unfortunately, the study only focused on potential reactor plant effects and not on the potential effects on dry cask storage. I concluded that the problem occurred due to inadequate design review for chemical compatibility.
i designer nor the licensee forsaw the potential for the chemical reaction that occurred. Several suggestions, that might have alerted the involved parties, were available. First, the paint manufacturer's specification sheet stated that the paint was not reccommended for immersion in acids. Secondly, the licensee studied the incompatibility of the paint and SFP boric acid in a study they conducted in July 1995. The study noted the potential for a zine borate pricipitate and possible coating on SFP fuel. Hydrogen generation was not addressed.. The study was a proactive effort and showed a good reflective atttude. Unfortunately, the study only focused on potential reactor plant effects and not on the potential effects on dry cask storage. I concluded that the problem occurred due to inadequate design review for chemical compatibility.
Ite m 6 Determine any notential generic implications of the event. Evalunie the technical supoort by the vendor for the prevention of similar events.
Ite m 6 Determine any notential generic implications of the event. Evalunie the technical supoort by the vendor for the prevention of similar events.
Preliminarily we determined the following potential generic issues as lessons learned from this event:
Preliminarily we determined the following potential generic issues as lessons learned from this event:
: 1. The adequacy.of the chemical compatibility studies conducted during design reviews for all cask designs and facility environments should be reviewed. For cases
: 1. The adequacy.of the chemical compatibility studies conducted during design reviews for all cask designs and facility environments should be reviewed. For cases
                      - where a detailed review was not conducted appropriate action should be taken.
- where a detailed review was not conducted appropriate action should be taken.
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              .                                                                                                                    l l
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,              2.       The potential for the presence of chemical reaction residues on fuel and storage cask components currently in day storage should be assessed. Additionally, the                                   )
2.
acceptability of any effects of the residue should be assessed for the remainder of the                           '
The potential for the presence of chemical reaction residues on fuel and storage cask components currently in day storage should be assessed. Additionally, the acceptability of any effects of the residue should be assessed for the remainder of the interim storage period.
interim storage period.
3.
:                3.
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                                                                                                . . . . _ . ~ . _ . . . . _ .
.... _. ~. _.... _
t.r                                                                                                                                                   i POINT BEACH QUESTIONS
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    ,                  For John Jankovich:
POINT BEACH QUESTIONS For John Jankovich:
OUR AIT CHARTER ITEMS 5 &6 ARE: (5)TO DETERMINE IF APPROPRIATE ATTENTION WAS GIVEN TO THE CONDITION OF COMPONENTS AND THEIR COMPATIBILITY WITH SPENT FUEL POOL CONDITIONS AND (6) DETERMINE ANY GENERIC ISSUES, AND EVALUATE THE TECHNICAL SUPPORT BY SNC FOR THE PREVENTION OF SIMILAR EVENTS The SNC inspection team should focus on items 5 and 6 and the following specific questions.                                           f j
OUR AIT CHARTER ITEMS 5 &6 ARE: (5)TO DETERMINE IF APPROPRIATE ATTENTION WAS GIVEN TO THE CONDITION OF COMPONENTS AND THEIR COMPATIBILITY WITH SPENT FUEL POOL CONDITIONS AND (6) DETERMINE ANY GENERIC ISSUES, AND EVALUATE THE TECHNICAL SUPPORT BY SNC FOR THE PREVENTION OF SIMILAR EVENTS The SNC inspection team should focus on items 5 and 6 and the following specific questions.
: 1. Did the SNC design review include a corrosion engineer. Should the designers have   .
f j
anticipated the Hydrogen generation in the SFP?
: 1. Did the SNC design review include a corrosion engineer. Should the designers have anticipated the Hydrogen generation in the SFP?
: 2. What was the design basis for the paint selection? Reference the COC pg A-2 " potential                                           ;
: 2. What was the design basis for the paint selection? Reference the COC pg A-2 " potential for fire and explosion should be addressed." and SER Sect 2.6. What environmental
for fire and explosion should be addressed." and SER Sect 2.6. What environmental                                                   -i compatibility study was done? How did they address the paint specification proldbition against the use of Zine with acid?
- i compatibility study was done? How did they address the paint specification proldbition against the use of Zine with acid?
: 3. What is SNC's investigative plan for this event'?
: 3. What is SNC's investigative plan for this event'?
l
: 4. Was their Part 21 evaluation performed? Were we and the customers notified?
: 4. Was their Part 21 evaluation performed? Were we and the customers notified?
: 5. Was SNC aware of the licensee's concern with the effect of Zinc accumulation in the                                               i SFP (from the MSB) in July 1995. What was their assessment and action?                                                                 !
: 5. Was SNC aware of the licensee's concern with the effect of Zinc accumulation in the i
n,           6.        Why was the paint not considered important to safety?                                                                       I
SFP (from the MSB) in July 1995. What was their assessment and action?
      .'            7. Was SNC aware of MSB lid welding problems (moisture and blowouts) enchntered at                                                     4 g               Palisades? What was their action?
6.
h
n, Why was the paint not considered important to safety?
..V
I 7.
: 8. Reportedly the paint was qualified at Oak Ridge. What were the paint qualification requirements?
Was SNC aware of MSB lid welding problems (moisture and blowouts) enchntered at 4
: 9. The SAR Pgs 1-8,1-9 state the purpose of the paint was to " protect fuel pool I               chemistry." What was meant by this statement.
g Palisades? What was their action?
h 8.
Reportedly the paint was qualified at Oak Ridge. What were the paint qualification
..V requirements?
: 9. The SAR Pgs 1-8,1-9 state the purpose of the paint was to " protect fuel pool I
chemistry." What was meant by this statement.
: 10. Is SNC involved with the VSC-24 user's group?
: 10. Is SNC involved with the VSC-24 user's group?
NOTE for John: Wisconsin Electric is authorized by SNC to fabricate their own VSC-24's.
NOTE for John: Wisconsin Electric is authorized by SNC to fabricate their own VSC-24's.
Line 215: Line 274:
O g,
O g,
For Charlie liaughney 1.
For Charlie liaughney 1.
Please arrange to have the team briefed on the VSC-17 problems with hydrogen addressed by Fawn Shillingslaw. .We need to have a cohesive story on why those problems did or did not relate to the VSC-24 problem.
Please arrange to have the team briefed on the VSC-17 problems with hydrogen addressed by Fawn Shillingslaw..We need to have a cohesive story on why those problems did or did not relate to the VSC-24 problem.
2.
2.
What did the NRC design review include? Was the chemical compatibility of paint /SFP water included? Does the SRP have an item on this? We expect this question after the exit. Will someone fandliar with the review process be at the exit ?
What did the NRC design review include? Was the chemical compatibility of paint /SFP water included? Does the SRP have an item on this? We expect this question after the exit. Will someone fandliar with the review process be at the exit ?
3.
3.
Please have a chemist review the chemical reaction that occurred. Are there ways to mitigate / prevent the reaction with PH control, etc.
Please have a chemist review the chemical reaction that occurred. Are there ways to mitigate / prevent the reaction with PH control, etc.
e i
e
I


Status ofIncident Investigation Hydrogen Burn During Loading of Third VSC-24 Investigation Scope and Status:
Status ofIncident Investigation Hydrogen Burn During Loading of Third VSC-24 Investigation Scope and Status:
    - Root Cause Evaluation Main effort thus far has been data gathering and interviews. Preliminary events and causal factors chart completed (6/5). Investigation team consensus is that the root cause lies in design issues category. This is based on preliminary review of the investigation into why CZ-i l was being used as a coating for the VSC-24 internals. Additional analyn of all causal factors is in progress.
- Root Cause Evaluation Main effort thus far has been data gathering and interviews. Preliminary events and causal factors chart completed (6/5). Investigation team consensus is that the root cause lies in design issues category. This is based on preliminary review of the investigation into why CZ-i l was being used as a coating for the VSC-24 internals. Additional analyn of all causal factors is in progress.
    - Source of Gas Substantial evidence has been gathered that shows the source of gas to be hydrogen produced by Zinc-Acid reaction. No substantial evidence has been found that would gove any of the following theories directly contributed to the production of hydrogen:
- Source of Gas Substantial evidence has been gathered that shows the source of gas to be hydrogen produced by Zinc-Acid reaction. No substantial evidence has been found that would gove any of the following theories directly contributed to the production of hydrogen:
Faulty Carbo Zine iI paint Contamination of CZ 11 paint Improper Application of CZ lI paint Radiolysis production of112 gas inadvertent introduction Combustible gas during loading process Welding issues Review of welding issues has not revealed any direct contributor to this event.
Faulty Carbo Zine iI paint Contamination of CZ 11 paint Improper Application of CZ lI paint Radiolysis production of112 gas inadvertent introduction Combustible gas during loading process Welding issues Review of welding issues has not revealed any direct contributor to this event.
    - Experience at Utilities Palisades is considered the most relevant experience to compare. Two Consumers Power dry storage e.sperts arrived on 6/5/96. Further analysis of differences and similarities is needed and is proceeding.
- Experience at Utilities Palisades is considered the most relevant experience to compare. Two Consumers Power dry storage e.sperts arrived on 6/5/96. Further analysis of differences and similarities is needed and is proceeding.
Review of Precursors Four Precursors have been identified:                                                           .
Review of Precursors Four Precursors have been identified:
Small burn during grinding in 2nd cask loading.
Small burn during grinding in 2nd cask loading.
Indication of pressure build up on 2nd cask after installation of shield lid.
Indication of pressure build up on 2nd cask after installation of shield lid.
Line 234: Line 292:
Visual Evidence of gas production.
Visual Evidence of gas production.
An additional possible precursor is: Film' residue seen during initial filling of MSBs i
An additional possible precursor is: Film' residue seen during initial filling of MSBs i
                                                                                                                  /M
/M


Incident Investigation Process
Incident Investigation Process 1.
: 1. Investigation Planning e    identify personn-l involve
Investigation Planning identify personn-l involve e
* Develop a preliminary E&CF chart Identify objective (s) of the Incident Investigation team e    identify areas requiring investigation
Develop a preliminary E&CF chart Identify objective (s) of the Incident Investigation team identify areas requiring investigation e
: 2. Information Collection a    Collection of physical evidence
2.
          . Interviewing of personnel e    Collection of records, logs, drawings, etc
Information Collection Collection of physical evidence a
: 3. Determine Sequence of Events e    Develop a detailed E&CF chan
Interviewing of personnel Collection of records, logs, drawings, etc e
: 4. Identify events causal factors / conditions
3.
          . Barrier Analysis
Determine Sequence of Events Develop a detailed E&CF chan e
* Change Analysis
4.
: 5. Identify Root Cause(s) e    includes identification of any " generic" causes
Identify events causal factors / conditions Barrier Analysis Change Analysis 5.
: 6. Develop correctise actions
Identify Root Cause(s) includes identification of any " generic" causes e
: 7. Report development                                       .
6.
Develop correctise actions 7.
Report development


POINT BEACH VSC-24 STORAGE CASK EVENT - MAY 28, 1996 DISCUSSION e       ' Event Followuo
POINT BEACH VSC-24 STORAGE CASK EVENT - MAY 28, 1996 DISCUSSION e
              -        AIT Findings & Conclusions
' Event Followuo AIT Findings & Conclusions Vendor Inspection Findings Sumary of Public Concerns hitial Reaulatory Acticas 6
              -        Vendor Inspection Findings
Issued IN 96-34 on May 31, 1996, CALs Issued June 3. 1996 to Affected Licensees (Pt. Beach. Palisades ANO).
              -        Sumary of Public Concerns 6          hitial Reaulatory Acticas
Future Reaulatory Actions e
                -        Issued IN 96-34 on May 31, 1996,                                   -
Generic Comunications:-
CALs Issued June 3. 1996 to Affected Licensees (Pt. Beach. Palisades ANO).
Cask Vendors Utilities operating or planning ISFSIs Modify SRP for-Storage Casks b
e            Future Reaulatory Actions Generic Comunications:-
Cask Vendors
                          -        Utilities operating or planning ISFSIs
                  -      Modify SRP for- Storage Casks b
x%
x%
L_
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A Good rning and welcome to this exit meeting following the completion of the NRC Mit     I am Roy Caniano, Chief of the Plant Support Branch in Region III. Over the eam leader for this inspection effort.
A Good rning and welcome to this exit meeting following the completion of the NRC Mit I am Roy Caniano, Chief of the Plant Support Branch in Region III. Over tYe past ten days I also served aj% t0 7ipM s the eam leader for this inspection effort.
tYe past ten days I also served     H          aj% t0 7ipM s l
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4 tris is tne fui v i u n iur we wrr and = standard policy fcr the';c type:; of
4 tris is tne fui v i u n iur we wrr and = standard policy fcr the';c type:; of p
,j p           spe
' meetinal inspe on, his open for puou servation. For, he pur ose of this spe t
            ' meetinal inspe t
discussi our inspec ings will be b n the NRC and
on , his discussi open for puou our inspec servation. For, he pur ose of this ings will be b       n the NRC and p, y           Point           Fol   ing the s ~ ns we wil       en       ed to opc       floor for y ques         any observe     ma     ave. To ass       his effort, Jack r.obe, D uty Divis,on D1       tor fr     Region III will facilita         that portion of the meeting.
,j p, y Point Fol ing the s ~ ns we wil en ed to opc floor for y ques any observe ma ave. To ass his effort, Jack r.obe, D uty Divis,on D1 tor fr Region III will facilita that portion of the meeting.
At this time I would like to go through a round of introductions of both NRC and Point Beach staff. (INTROS...)
At this time I would like to go through a round of introductions of both NRC and Point Beach staff. (INTROS...)
Thank You. Before we get started with further discussions, and for the benefit of attendees that may not be familiar'with dry cask operations and the event that occurred here on May 28, Tim Kobetz, the Senior NRC Resident Inspector here will give a brief overview of the cask system utilized here at Point Beach and will briefly summarize the event. As findicated earlier, I would appreciate that any questions arising from the summ4ry be held until later.
Thank You. Before we get started with further discussions, and for the benefit of attendees that may not be familiar'with dry cask operations and the event that occurred here on May 28, Tim Kobetz, the Senior NRC Resident Inspector here will give a brief overview of the cask system utilized here at Point Beach and will briefly summarize the event. As findicated earlier, I would appreciate that any questions arising from the summ4ry be held until later.
(TIM'S OVERVIEW)
          - / Thank you Tim.
f
((
((
I I      Last Thursday was the formal initi Point Beach management. At that ion of the fkt/and the entrance meeting with me we summarized the principle reason for the I       ')W which was attaining an un rstanding of the root cause of the hydrogen generation causing the -hydrogen burrr during the welding operation on May 28th.               ,
(TIM'S OVERVIEW) f
t            In addition at the entrance meeting we also discussed several other objectives g       These included :                                                             V).
- / Thank you Tim.
, M J In addition to the NRC staff here at Point Beach we also had several NRC staff m24           members at the Sierra     Nuclear facility in California. Sierra Pcle:Hs4he AMY -designeMor--the-cask-system-used-here-at Point-Beach. C,/2
I Last Thursday was the formal initi ion of the fkt/and the entrance meeting with I
    ,        We believe that over the past week and a half that we have gained a good understanding of the root cause of the event as well as an understanding of the circumstances leading up to the event. In addition,we were also able to assess, by direct observations, your initial response activities immediately following the event. As you are aware, Tim Kobetz followed the event immediately after its occurrence with additional NRC staff being dispatched from Region III, soon after we became aware of the event. Until the cask was safely moved back into the spent fuel pool NRC provided round the clock oversight.
Point Beach management. At that me we summarized the principle reason for the I
I would now like to provide a general overview of our assessment of the event as well as the circumstances leading up to the event and your response to it. I will then turn the discussions over to each of the/4Wteam members introduced earlier who will provide a more detailed summarization of our findin s.
')W which was attaining an un rstanding of the root cause of the hydrogen generation causing the -hydrogen burrr during the welding operation on May 28th.
770 W Our initial evaluation of the event confirmed that the/e were no releases of                     !
In addition at the entrance meeting we also discussed several other objectives V) t g
radioactive materials from the cask following the b ey ouen h en and no increase                 !
These included :
in radiation levels surrounding the cask. As                                                     I employees the environment or members of the public.such there was no \ptEF                       l 7
, M J In addition to the NRC staff here at Point Beach we also had several NRC staff m24 members at the Sierra Nuclear facility in California. Sierra Pcle:Hs4he AMY -designeMor--the-cask-system-used-here-at Point-Beach. C,/2 We believe that over the past week and a half that we have gained a good understanding of the root cause of the event as well as an understanding of the circumstances leading up to the event. In addition,we were also able to assess, by direct observations, your initial response activities immediately following the event. As you are aware, Tim Kobetz followed the event immediately after its occurrence with additional NRC staff being dispatched from Region III, soon after we became aware of the event. Until the cask was safely moved back into the spent fuel pool NRC provided round the clock oversight.
I would now like to provide a general overview of our assessment of the event as well as the circumstances leading up to the event and your response to it.
I will then turn the discussions over to each of the/4Wteam members introduced earlier who will provide a more detailed summarization of our findin s.
770 W Our initial evaluation of the event confirmed that the/e were no releases of radioactive materials from the cask following the b e ouen h en and no increase y
in radiation levels surrounding the cask. As I
employees the environment or members of the public.such there was no \\ptEF 7
N1
N1


h O
h O
Although some #Gihvweaknesses we           identified during re         ery operations which will be discussed later, overall, your raspense and af-f                     returning the cask               ~
Although some #Gihvweaknesses we identified during re ery operations which will be discussed later, overall, your raspense and af-f returning the cask
to the spent fuel pool,4 W W -                                                       a~v d Ifg/IWithregardtotheeventitselfandasTimipdcatedearlier,thec
~
      .bes(on the welding of the third c sk was Me rxM af hydrogen se of the present           p l
to the spent fuel pool,4 W W -
()   at the location of one of the               wel   . The hydrogen was pr           nt as a result                     i of the chemical reaction when the during loading operations. Basef pon ntfuelpoolwaterwasaddedtothecaskf our review of the pr ious two cask loads 4                          r,  l we    also  determined    that  thereillas  ev3Me+      h of t!.e sec^ " M tt .:x:: ^" ' - s Thk D=+cgen generait meing:Imrdimy                               .J
a~v d Ifg/IWithregardtotheeventitselfandasTimipdcatedearlier,thec se of the
                                                                                          ---- =lhe inp        t of#^ ~^ " -"' "ith- = ve =:ac;;...m n u,;M-W-                       C'    .
.bes(on the welding of the third c sk was Me rxM af hydrogen present p
                                                                                          % h necurred
()
                                                                                                                        ' U l I
at the location of one of the wel
witd ''43 ---99                                             ev.idencA th:t. g ev tku t wiUi me ivauing or 4
. The hydrogen was pr nt as a result of the chemical reaction when the ntfuelpoolwaterwasaddedtothecaskf during loading operations. Basef pon our review of the pr ious two cask loads of t!.e sec^ " M tt.:x:: ^" ' - s Thk D=+cgen generait meing:Imrdimy
                                          .![o s hm e  ha--
' t
E    . 7,;
' U l 4
9 ;;; 3 r            y   Jj ) '  i p
r, we also determined that thereillas ev3Me+ h
Although these problems were n ed by severa a'-                     ~ 'ayees involved in
.J of#^ ~^ " -"' "ith- = ve =:ac;;...m n u,; C '
* the loading of the aneombcask.rthere was limited followup to the occurrences in an attempt to identify the causes.
---- =lhe inp M-W-
i,    N( '
% h necurred I
witd ''43 ---99
.![o s hm e ha--
ev.idencA th:t. g 9 ;;; 3 r J ) '
ev tku t wiUi me ivauing or 4 E
. 7,;
y j
i p
N( '
Although these problems were n ed by severa a'-
~ 'ayees involved in the loading of the aneombcask.rthere was limited followup to the occurrences in i,
an attempt to identify the causes.
Had a detailed technical review been accomplished you may have identified hydrogen was present and as such, it is quite possible that the event with the third cask could have been prevented.
Had a detailed technical review been accomplished you may have identified hydrogen was present and as such, it is quite possible that the event with the third cask could have been prevented.
n At this time I would like each of the individual                   . staff members to summarize                         I their inspection findings and identify any issues that will warrant additional                           '
n At this time I would like each of the individual
l followup. Following each summary I would request that you respond to our assessment.                                       ,
. staff members to summarize their inspection findings and identify any issues that will warrant additional followup. Following each summary I would request that you respond to our assessment.
                                                                              ~
~
Closing:           you for           1me today. The, re ort 1inmarizing our fi Trg's wi3J -
~~
                                                                                                    ~~
Closing:
be           within t       xt three weeks.           s indicated,there w           ever     ems ill warrantin followup.         Thesa       be identifieo in the nspect               report.
you for 1me today. The, re ort 1inmarizing our fi Trg's wi3J -
for this   time the exit M is concluded.
be within t xt three weeks.
estions form members o I uld now like to en the meeting e public or medi . s previously 1             cated Jack Grobe wi         facilitating that e           and at this tfiil         would like to rn the       i/p    d meeting over to a(                                                                                   P//
s indicated,there w ever ems ill warrantin followup.
                                                                                                }"l                   j a-                          D e g #                                                   'Y? J l',
Thesa be identifieo in the nspect report.
a s (, y *" R - q p r<
this time the exit M is concluded. I uld now like to en the meeting for estions form members o e public or medi.
vaN. sau                -
s previously 1 cated Jack i/p Grobe wi facilitating that e and at this tfiil would like to rn the d
meeting over to a(
P//
}"l j
D e g #
'Y? J l',
a-a s (, y *" R - q p r<
va sau N.


l bem b                                     hebc. [W65                                                                                                                 l h
l bem b hebc. [W65 h
I                         Number 1.
I Number 1.
The adequacy of the chemical compatibility studies conducted during design reviews for all cask dcrigns and facility environments should be reviewed. For
The adequacy of the chemical compatibility studies conducted during design reviews for all cask dcrigns and facility environments should be reviewed. For cases where a detailed review was not conducted, appropriate action should be taken.
;                                            cases where a detailed review was not conducted, appropriate action should be taken.
$ Examples versights i ntified from thi event inc the po ' bili]ty of the tion
                                      $ Examples                             versights i ntified from thi event inc                     the             tion
'h ogen from inc paint -
                                        'h ogen from inc paint - borated water etion,                                                     the po ' bili]ty              of      j i                                           water ~               sion in             id's shieldi   material (in               desig         [ Thia                           l includes                         dy of the etting of       Q7 which occ gat Pal                             an                   j
borated water
( ANOl l
: etion, j
Number 2.       The potential for the presence of chemical reaction residues and other foreign material on fuel and storage cask components currently in dry storage should be assessed. I say the " potential" for the presence of material because                                                             ;
i water ~
although it is fairly certain that these Point Beach casks have residue it is not                                                     !
sion in id's shieldi material (in desig
yet clear whether other cask systems would have unanticipated materials.
[ Thia l
l Additionally, the acceptability of any effects of the residue should be assessed.                                                     i Number 3.       The cask evolutions introduced ionic zine and silica into the spent fuel pool.
includes dy of the etting of Q7 which occ gat Pal j
an
( ANOl Number 2.
The potential for the presence of chemical reaction residues and other foreign material on fuel and storage cask components currently in dry storage should be assessed. I say the " potential" for the presence of material because although it is fairly certain that these Point Beach casks have residue it is not yet clear whether other cask systems would have unanticipated materials.
Additionally, the acceptability of any effects of the residue should be assessed.
i Number 3.
The cask evolutions introduced ionic zine and silica into the spent fuel pool.
Consequently, ionic zine and silica were introduced into the reactor coolant system from the spent fuel pool. Although tilis can be controlled, the amount of zinc and silica introduced and acceptability limits should be determined.
Consequently, ionic zine and silica were introduced into the reactor coolant system from the spent fuel pool. Although tilis can be controlled, the amount of zinc and silica introduced and acceptability limits should be determined.
Likewise, for other cask systems any material introduced into the spent fuel pools which have a potential for entering the reactor coolant system should be assessed.                                                 -
Likewise, for other cask systems any material introduced into the spent fuel pools which have a potential for entering the reactor coolant system should be assessed.
Number 4       The suitability of this.Daint,in other nuclear applications where exposure to boric acid is a potential should be re-reviewed. We have considered the effects of hydrogen generation in containment applications but a broader review may be in order.
Number 4 The suitability of this.Daint,in other nuclear applications where exposure to boric acid is a potential should be re-reviewed. We have considered the effects of hydrogen generation in containment applications but a broader review may be in order.
Number 5       The adequacy of cask cleanliness controls should be assessed generically .
Number 5 The adequacy of cask cleanliness controls should be assessed generically.
[The casks were not cleaned with water before immersion and soap was introduced during the decontamination process.]
[The casks were not cleaned with water before immersion and soap was introduced during the decontamination process.]
i-                       .                                                                                                  _
i-I Third, I Evaluated the technical suonort by the vendor for the orevention ofsimilar events.
Third, I Evaluated the technical suonort by the vendor for the orevention ofsimilar events.                                                       I After the event, the                                  ner, Sierra Nuclear, had an        rations engineer onsite
{
{
pro ' e technical expertise and                           ist in the unloading of the       k. Additionally, freque elepho conference calls were hel                                 ith Wisconsin Electric sta and Sierra Nuclear A Jgners i         lifornia to discuss technic issues. Additionally, sta from Palisades and
After the event, the ner, Sierra Nuclear, had an rations engineer onsite pro ' e technical expertise and ist in the unloading of the
                        %ansas Nuc cat (other users of the cask) h                             participated in the telep                 conferences.
: k. Additionally, freque elepho conference calls were hel ith Wisconsin Electric sta and Sierra Nuclear A Jgners i lifornia to discuss technic issues. Additionally, sta from Palisades and
As Dr. Jankovich p iously stated, Sierra Nucl                                 as developed a detail ' vestigation and
%ansas Nuc cat (other users of the cask) h participated in the telep conferences.
                          'on plan but also the                   d some deficiencies in im             enting their design co of process.
As Dr. Jankovich p iously stated, Sierra Nucl as developed a detail
Consequ       we consider the tech (cal support provided by                                   Nuclear for this ev                   to be adequate.                                                                                                                                   _
' vestigation and
'on plan but also the d some deficiencies in im enting their design co of process.
Consequ we consider the tech (cal support provided by Nuclear for this ev to be adequate.
i
i
                                . , .  -_        -                    ~ _ . _      _      ._                          . . ~ .                 . , , _            _
~
.. ~.


- - - . _          _ .      _                      _ _ _ .                  .    . _    ~.             _    _. __ .          ..        _ ---_____
~.
                                                                                                                                      .        .~~-               "
. ~ ~ -
Aug-14-96 04:48P PBNP NRC Res idernt Office                                                                                                             -.-
Aug-14-96 04:48P PBNP NRC Res idernt Office 414-755-4374 07 NIMS
                  .                                                                                    414-755-4374                                                   07
/
                "                                                                                            NIMS
' CONDITION REPORT cEE /M, d[
                                                                                                                          /
q 3
                        ' CONDITION               REPORT                                                 cEE     q /M,
g,
          ! rw:ription
! rw:ription 30.
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Ab [kr}(93Mu'th                       les b3 NP 3 ,, W Q, a fsCb ' cant 'lQJECMn S b*i Nup On fhe bel t'c                                .
P 2 he 15 Q,
rtes.Olh        is id    Ce@
four melhny
oo (MQg                 gQQ "W _ _-
' nt theki S
ik. 9 Con =ctlye     'Fn w aacticos i            or pois. ,.complee9rl
Ab [kr}(93Mu'th is Ce@
                                                          ,,      Q          95 or la proTia ilj(1f a WO ea>,.
les b i
has been g     t.
rtes.Olh id 3
Ve>               < h4 no                                                                                                                                   ..
NP 3
ci, u.) Oppl.c Nahr, crec                   hcAb                           '
,, W,
a r.                                  uj eJt. n r-   S     . Einc . Lov melHn3 pnt meh .-
a fsCb ' cant 'lQJECMn Q
W*                                                                                .. 4
b*i Nup On fhe bel oo (MQg gQQ t'c "W _ _-;
          %4 h, , doY Sge b G C d, .{^ A -)G M . ,6 eftC.f GM.kck tat % Car %%'.n &
Con =ctlye acticos complee9rl or la proTia ilj(1f a WO has been t.
rstd.WAf M AIG .
ea>,.
Recomm odauoos           C o n h k 9.                                                                                                    ..
ik. 9 'Fn w a or pois.,.
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Q 95 g
                                                                                            ,ih6     c,.,   c(; @ c- e.ppj-                     M tuc Lthy pupses. Th.s hswt vdI                                           be     casJ             prior- to 5
i Ve>
fhe. MS6 tnto 4hR. 5 Ff.
< h4 no crec hcAb r-S
placA        3 %      -
. Einc.
Izferczeca                                                                                                                                               -
Lov melHn3 pnt meh.-
aisiator (Print namc/ dais) hA @. O _                                                   Def,n,/S ELes / 7-:IM Hased dedher ao ase mesher .sto tJasemed andMessifer amabissed s             -
ci, u.)
          'RO Review           Nose
Oppl.c Nahr, C d,.{^ A -)
                                      "./.. DSF '- "% yasser @ is amarted yes.
eftC.f GM.kck tat %
Car %%'.n &
.. 4 a r.
uj eJt. n W*
%4 h,,
doY Sge b G G M.,6 rstd.WAf M AIG.
Recomm odauoos C o n h k 9.
C.wereA+
INw h*y &,
,ih6 c,., c(; @ c-e.ppj-M tuc Lthy pupses.
Th.s hswt vdI be casJ prior-to 5
placA %
fhe.
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3 Izferczeca aisiator (Print namc/ dais) hA @. O _
Def,n,/S ELes / 7-:IM Hased dedher ao ase mesher.sto tJasemed andMessifer amabissed s
'RO Review Nose
"./.. DSF '- "% yasser @ is amarted yes.
a
a
                                                                                                                                      ~ % '. 9                       .
~ % '. 9 uny systena. structurce, or compoucats inoperabic7 O No O Yes w
uny systena. structurce, or compoucats inoperabic7                 O No     O Yes                                         w                             9 Further Evaluation Requirod .
9 Further Evaluation Requirod.
f
f
                                                                                                                                                      %i~         .
-%i~
I the C00ditl00 reportable 7 (Ref. DCS 2.1.1 or 2.1.2)             O N.       Ov                   Further Evahastion Required A
I the C00ditl00 reportable 7 (Ref. DCS 2.1.1 or 2.1.2)
Bh (SigE/Date)                                                                                                                           ,
O N.
Ov Further Evahastion Required A
Bh (SigE/Date)
Mame la work control centre CR beskat.
Mame la work control centre CR beskat.
df/AAna
df/AAna sw w
        . --._ <                            yg                                            _-~~             sw                      -
y
w g                        -
_-~~
                                                                                                                                                      =.
=.
        .: Manager Initial Review (Sign /Dess)
g g
Plant Manager Closcout Review (Sign /Date) 1552 anon 0 06/24/94                                                                                                                     ,,
.: Manager Initial Review (Sign /Dess)
Plant Manager Closcout Review (Sign /Date) 1552 anon 0 06/24/94


_ _                    _ __ __ _.                                  _ _ _ . . _ . _ . _ _ . _ _.                      ____.--m__._._________                                                         _ - _ .
____.--m__._._________
v e
v Aug-14-96 04:4BP PBNP NRC Re s 1 cie rit Office 414-755-4374
* Aug-14-96 04:4BP PBNP NRC Re s 1 cie rit Office                                                                                         414-755-4374
'"t-'08 e
                                                                                                                                                                                                    '"t-'08
e- - -- --
                                                                                                                                                              .      e- - -- --
c j*
c                     -
y M ITI31 R$i W bAM'h
j* .
@'fw/,5 n-I
M ITI31--.R$i W bAM'h         @'fw/,5 y . .-
~
n-I                                                                                   ~
! STATU5: CLOSED UIllT: 0 ST5fgMs $F INITIATE 0s 07/11/95 CL0$80: 07/26/95 Msg #
  ! STATU5: CLOSED 47tTIATOR: Otmult EVERS UIllT:   0     ST5fgMs $F INITIATE 0s 07/11/95                   CL0$80: 07/26/95                   Msg #
,jM.
                                                                                                                                                                                          ,jM.
47tTIATOR: Otmult EVERS A0048mISTRATOR: SCOTT PFAFF i NupmER OF OPEN ACTIOles t o 199ut MellAGER: $(XITT PF)F ausg8R OF CLOSED ACTIONS : 1 TOTAL InsseER OF ACTIONS't Multi Astestpty seated Booket Costing ites Potentist tg Leech Zing Into the Sptfit fuCl P001 DESCRIPTIdelt wee
i NupmER OF OPEN ACTIOles t o                                                       A0048mISTRATOR: SCOTT PFAFF                                                                                                          ,
~
ausg8R OF CLOSED ACTIONS : 1                                              199ut MellAGER: $(XITT PF)F TOTAL InsseER OF ACTIONS't
lt hee been dieeevered that the Cartmanic 11 coettne used on the nutt.eeeenesty seetess see l
* Multi Astestpty seated Booket Costing ites Potentist tg Leech Zing Into the Sptfit fuCl P001 DESCRIPTIdelt                                                                                                                                                                           .
~~
wee
sterser hoe the setentist to teach sinc into the egent fust poe,t teien tasserseet. Lets teachehltity c ste ha day w.f the ase outd v4eid. erP sine ~~entreuen up to 5pp.
                                                                                                                                                                                                          ~
$fgnificences Zinc is a teu sueltfne point metet which fe controlled try leP 3.1.9 l
                                                                                                                                                                                                          ~~
fus. essembties.
l              lt hee been dieeevered that the Cartmanic 11 coettne used on the nutt.eeeenesty seetess seem day
and hee the potentlet to ferti scale huitaiwp en 4
,            sterser       w .f  hoethe the     ase setentist outd v4eidto. erP  teach   sinesinc  ~~entreueninto theup    egent to 5pp.fust poe,t teien tasserseet. Lets teachehltity c ste ha l              $fgnificences fus. essembties.            Zinc is a teu sueltfne point metet which fe controlled try leP 3.1.9                                                                                                 .
mote:
and hee the potentlet to ferti scale huitaiwp en 4             mote:
A aCs sinc injection ettely sereducted et Feeley reeutted in en asteepeeted easte buttehge en fust rede j
j                          A aCs sinc injection ettely sereducted et Feeley reeutted in en asteepeeted easte buttehge                                                                       en fust rede
not have e specif teetten for ere sine sensentrattene. Cheetstry la surrently owelusting thle potentlet eendittet.
                                                                                                                                                                                        . %feettrighouse dose j            not      have e specif ove4essesen                   of 44 ase   teetten      for ere eseqstesed           sine preer       sesensentrattene.                Cheetstry any segg iesseny seetvtttto             in mela surrently        owelusting thle gfp gre geignonses                   potentlet  fnte.
. %feettrighouse dose ove4essesen of 44 ase eseqstesed preer se any segg iesseny seetvtttto in me gfp gre geignonses j
eendittet.
fnte.
ITATue UPDATE:                                                                                                                                                                                           ,
ITATue UPDATE:
;            (07/36/95 3AP) This Ca le belns closed hesed tgeen the sanctuelene of the evolustfort                                                                               performed try Ch ansineertne (see post 95 04A0 for detalle). N -ry of the evetuotten con tre seen taider                                                                         enfatTyT*
(07/36/95 3AP) This Ca le belns closed hesed tgeen the sanctuelene of the evolustfort performed try Ch ansineertne (see post 95 04A0 for detalle). N -ry of the evetuotten con tre seen taider evoluetten et unde N e't "
evoluetten       N e't       et  "unde i            ectlene ered    completed. taken for this inaue heve adequately addressed the oltuetten. This CA is belne closed bened                                                                                       othe upon u en
enfatTyT*
                                                                                                                                                                                                ~
ectlene taken for this inaue heve adequately addressed the oltuetten. This CA is belne closed bened upon i
i CittENES ST : SCOTT PFAFF                                                                                                                                                                                         g, i                                                                                  DATEe 07/13/95 treutATORT REPORTA4Lt. . .. .(Y/4): Il
othe ered completed.
;            TE      LC0..................                   .(T/N):   N T5 VIOLATION..............(Y/N): N                              10 Cpn 21.................(T/w):                                                 l W
u en i CittENES ST : SCOTT PFAFF
j          Mes agvigw..............                         .(Y/W); N            OPERA 31LITT EMPACT PER TI.(T/N)e W                              JC0 4toulaEO............                                                         {
~
3CAe......................(T/N):                   N COMN!Tastu f . . . . . . .0/ups s,    ,
g, DATEe 07/13/95 i
                                                                                                                                                                                        . . . . n. u. . . ( T/w ):
treutATORT REPORTA4Lt.....(Y/4): Il T5 VIOLATION..............(Y/N): N TE LC0..................
l l UPPDRTING e a s e seem DETERMINAi!DNS:
N OPERA 31LITT EMPACT PER TI.(T/N)e W l
d reportante event, currently westinghouse does not have any ser specificatione for                                                                                                     sineW concentrat is net'               "
10 Cpn 21.................(T/w): W j
conducted try Cheelstry to determine whether there is en actual concern recording the                                                                               .AnevetustionIlebing buildup of sinc                         scale on
Mes agvigw..............
,          In thJ 5FP. Pending the outcome of this Investigation ** edditionet coerective sneuures may be .uerrented                                                             .                   g*.O eaubtles 4EmplCC I2 FORMATION:
.(T/N):
k 40e g NCta-0UTAGE                                                                                                                                                                                   ~C^*
JC0 4toulaEO............
i     IQ_,,,,.       WUDOQ                                                                                                 THtRD QUARTER OF 1995 47                                                                                                                                                                                                 E I    (AC:. PtookSH WAe esof AseTictr4TCD tente ecslestCD CIU 151RT RELATED
{
                                                                                                                                                                                                          =~
.(Y/W); N 3CAe......................(T/N): N COMN!Tastu f............... ( T/w ):
1 *$ttn 3rtNT futL COOLING end FILTRATION                                                                                                                                                                   -
s, l
*                                                                                                                                                                                                          -                        )
0/ups n u l UPPDRTING DETERMINAi!DNS:
i                                                                                                                                                                                                             -
e a s e seem reportante event, currently westinghouse does not have any ser specificatione for sine concentra d
j'FEtt:CES: hP 3.1.1                                                             PeM 95 0460                                                                                                                                         1 I                                                                                                                                                                                                                      ,            l
is net' W "
;                                                                                                                                                                                                                                    I i
conducted try Cheelstry to determine whether there is en actual concern recording the buildup of sinc scale on  
                                                                              .C.A 95-358
.AnevetustionIlebing In thJ 5FP. Pending the outcome of this Investigation ** edditionet coerective sneuures may be uerrented eaubtles
:: z            - _ _......ACT!0N
. g*.O 4EmplCC I2 FORMATION:
                                                                                                                  .: x      .tlupot.e.se..1 l
k 40e g NCta-0UTAGE
as                                                                                                                                                                                                                             j
~C^*
; eat 2 e OP/13/tp Ott                                     sus e4Tes er/ sins                                      resseerve .tes                                                                                                  !
i IQ_,,,,.
GC0ft NAFF                                                                                           enTemescue mRees t
WUDOQ THtRD QUARTER OF 1995 E
* 1 RK DQuts                                                 FCLICIA pessNsEssY                                      R$CllVfDI 07/19/M                   CH       FtLtr.lA heleittty E! PIED : 07/26/95                                   SCOTT PFAFF                                             APPROVED: 07/21/95                          FELICIA MEINfESSFA CLotto a 07/36/95                                                               3 SCOTT PFAFF L
47
1 i sistunts essemblite      tha in  potential the Spentef            fects Fuel      that Poet.          the Certoonic Determine                enr necessary  11 M84     coating corrective            and teached measures          as        Ilnc concentration e                        in the Spent appropriate.                       ost egerve on                           j i 807/19/95 FPN) Received Actlen Inte ereups cet
. PtookSH WAe esof AseTictr4TCD tente ecslestCD I (AC: CIU 151RT RELATED
! Responeltte Pereen FPW:FSLICIA II0lHISatY                                                                                                                                                             - .*
=~
! *$ttn 3rtNT futL COOLING end FILTRATION
)
1 i
j'FEtt:CES: hP 3.1.1 PeM 95 0460 1
I
.C.A 95-358 - _ _......ACT!0N tlupot.e.se..1 l
:: z
.: x i'
j as sus e4Tes er/ sins resseerve.tes
; eat 2 e OP/13/tp Ott GC0ft NAFF enTemescue mRees t 1 RK DQuts R$CllVfDI 07/19/M CH FtLtr.lA heleittty FCLICIA pessNsEssY APPROVED: 07/21/95 FELICIA MEINfESSFA E! PIED : 07/26/95 SCOTT PFAFF CLotto a 07/36/95 SCOTT PFAFF L
3 1 stunts tha potential ef fects that the Certoonic 11 M84 coating and teached Ilnc concentration in the Spent i si essemblite in the Spent Fuel Poet. Determine enr necessary corrective measures as appropriate.
ost egerve on j
e i 807/19/95 FPN) Received Actlen Inte ereups cet
[
! Responeltte Pereen FPW:FSLICIA II0lHISatY Ove Date: 07/31/99 i
i 107/21/95 FPit) cheeletry hee sempleted en ewetuotten of the use of sortealns es a primer for the M00s. This evet
/
j doenmented in PeM 95-0440. The evoluetten Cencluded titet White it le seceptable to use the ti.e Mete uhleh lie asinted trith cerherine, un should net une the eschemine point in the future ts11eoe ett surfaces pr11gg 1
ve elrse. u n i
Pesolue a ese use ad u-
. e-
- t s 6 4-. -.= -.. w ws e r enemissry netos to sainte the scen hgg siga enagjnt j
mee 6.
b A-.re.d en she poes. a t neon tevoto et atne are toen, ese need to ensure that the opent fust poet le ust i.
through the spent fust poet deelne mtit the sine to resueved. (An activity hee been plesed i rwy cQtated 4
ensure thle happene.) 2) fuel prior to releeding it in the core. 3) um need to ensure that cerbesinc coated with epony n the shutdeun resolutfeh.6 et to sultet>te etternettve.
4 oesn't teoch end/or find.e
.' (07/I1/95 PPn) Pessocf to SCOTT PFAFF for Verf fication.
9 (07/2&/95 149) DLA Ctesure ed 34.ai.
[
[
i Ove Date: 07/31/99
N evslust100 dissunsec In PeM 95 06&O have been reviewed and the renomseendetiene end sanctusta i
* i 107/21/95 j doenmented FPit)            in PeMcheeletry  95-0440.        hee sempleted en ewetuotten of the use of sortealns es a primer for the M00s.                                                          /                This evetu 1                                                            The evoluetten Cencluded titet White it le seceptable to use the ti.e Mete uhleh lie asinted              trith        cerherine,        . e-un should net une the eschemine point in the future ts11eoeve                                                            ettelrse.
aatten leen 4 Chemierry tube) to destruf ne the zinc concentrattswie (and ensure that they are ecceptible) ha the teenefer e eeund..an posetutten List for the felt refueline outsee.
surfaces      un            pr11gg i
4 Ne additlenet actime are necessary et this time. Closed.
j        Pesolue            a  ese      use        ad u-mee 6.            b                                            - t s 6 4- . -.= - .. w ws e r enemissry netos to sainte the scen hgg                                              ust            siga i . enagjnt through            the      A-.re.d en she poes. a t neon tevoto et atne are toen, ese need to ensure that the opent spent fust                                                                                                                                                      fust        poet le 4        ensure        thle  happene.)              2) poet deelne mtit the sine to resueved. (An activity hee been plesed i                                                                        rwy cQtated n the shutdeun resolutfeh.6 et to 4        fuel prior sultet>te                    to releeding etternettve.                            it in the core. 3) um need to ensure that cerbesinc  .
e o the Shutdown 4
coated with epony oesn't teoch end/or find.e
dB
.' (07/I1/95 PPn) Pessocf to SCOTT PFAFF for Verf fication.                                                                                                                                                9 (07/2&/95 149) DLA Ctesure ed 34.ai.                                                                                                                                                              [
i      N evslust100 aatten        leen 4 Chemierry      dissunsec In PeM                     95 06&O have been reviewed and the renomseendetiene                                                     e eeund..an end sanctustan the teenefer 4
posetutten List            tube)   for the    tofelt destruf refuelinene  outsee.the zinc concentrattswie (and ensure that they                                                           are ecceptible)                         ha!
Ne additlenet actime are necessary et this time. Closed. e o the Shutdown                                     '
4 dB


i -                                                                                                         .
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        .Au3-14.96 04:49P PBNP NRC Resident Office 414-755-4374
.Au3-14.96 04:49P PBNP NRC Resident Office 414-755-4374
                                                                                                          ~
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trer.cuers: Pen 95 0460                                                                                             -
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Aug-14-9G 04249P PONP NRC Renident Of'1' i c e                                                                                                                     ..~.
.. ~.
              ~
Aug-14-9G 04249P PONP NRC Renident Of'1' i c e 414-755-4374 -
414-755-4374 -
'o
                                                                                                                                                                        'o
~
                    .                            NUCLEAR POWER DEPAR'INENT
NUCLEAR POWER DEPAR'INENT
                                                                                                                                          ~' g -                           '
~' g -
Screening Results IDENTIFIER (trkid)                   CR 95_358                               -                                                                              b
Screening Results IDENTIFIER (trkid)
                                                                                                                                                                      /
CR 95_358 b
1 INITIATOR:             Dcr,     - DgutfIS EVERS                                   S                                                                     *
/
                  . . . . . - - _ . . . - - - - - - - . - - - _ - - - - - - - _ - _ _ oURCE DOCUMENT DATE : 07/2lCClrs
INITIATOR:
                                                                                                -----__---... -- . -- f_                                                   ..
: Dcr,
1 SCREENING RESULTS:                                                                                                                     '
- DgutfIS EVERS S
..... - - _... - - - - - - -. - - - _ - - - - - - - _ - _ _ oURCE DOCUMENT DATE : 07/2lCClrs
-----__---... --. -- f_
SCREENING RESULTS:
(Y/N)
(Y/N)
                                                                    --_--                                                                                            N)
N)
Regulatory Reportable.....                             H
Regulatory Reportable.....
,                10 CFR 21.................                             N TS Violation..........
H TS Violation............. @
TS LCO..:.................
10 CFR 21.................
N Operability. Impact per TS.                           N                 JCO Required.............. .N                                                       I MSS Review................                           N                                                                                                       l SCAQ...................... [N                 .                                      l COMMENTS SUPPORTING SCREENING DETERMINATIONS:
N TS LCO..:.................
This licer) event           is not a violation sing commitment                  to the NRC of anyand  PBNP it i ? .:hnical Soecifications era.-
N Operability. Impact per TS.
W2stinghousse dges not have an                                                      not a reportable.even                                     ryently An       evaluation       la   being conduc             ed   bvSFP         eoneci      ications         tordetermine za.nc cwnc. en . acionb.e en     actual   concern     regarding     t e bull   up of zinc,   scale         fuehem         stry to                 ethW2t:.                   re           s thn SFP.
N JCO Required..............
Pending         the outcome of th:.s investigation -- additional corre.cn;s':::;n                       asse mansures may             be warranted.                                                                                                                 i:Crve
.N I
MSS Review................
N SCAQ......................
[N COMMENTS SUPPORTING SCREENING DETERMINATIONS:
This event is not a violation of any PBNP ?.:hnical Soecifications era.-
licer) sing commitment to the NRC and it i not a reportable.even ryently W2stinghousse dges not have an An evaluation la being conduc ed bvSFP e eci ications tor za.nc c nc.. acionb.e en en actual concern regarding t e bull up of zinc, scale on fuehem stry to determine w ethW2t:. re s
thn SFP. Pending the outcome of th:.s investigation -- additional corre.cn;s':::;n asse mansures may be warranted.
i:Crve


==REFERENCES:==
==REFERENCES:==
                                                                                                                                                  'h NP 3.1.1                                                                                                                                       o
'h NP 3.1.1 o
                                                                                                                                                      \*       ,
\\*
a-
a-
                                                                                                                                                    . .L . ..-
..L...-
_. j,, , ,
_. j,,,,
:.aCJst .                ***
:.aCJst
                                                                                                                                            -~r-~._,.-
-~r-~._,.-
                                                                                                                                                      ~3 e                   A               *
~3 e
:2c.:::::c il       .
A
T* '"w
:2c.:::::c il T* '"w
                                                                                                                                                            . .d '
..d '
i_,
i_,
    ....................................................................e.
t
t SCREENED BY                   SAP -           SCOTT PFAFF                   .w.t 7 J                                                                                                                                                       .-
....................................................................e.
SCREENED BY SAP -
7 SCOTT PFAFF
.w.t J
S
S
                                                                .....I.ONATURE O
.....I.ONATURE O


Aud-14-90 04:47P P5NP NRC Resident Office                                   414-755-4374                         I                   04 5
Aud-14-90 04:47P P5NP NRC Resident Office 414-755-4374 I
y                    _
04 y
: 7. .           /  ,
.'L 5
        *  .'L                                                                                                      .M. c i j,7                       j OA                                   .
/
                                                                                                          -*EE NIMS --.. Y .~2. -                         _
: 7..
PBM 95 0460                                                     M_                e TO:       K. R. Anundson P377                                                                           M R. D. Bronk                   W. J. Hennestyy                                              -
.M. c i j,7 j
: c. A. Castell P377 N. L. Hoefert FROM:       F. P. Hennessy D. C. Ryggs M. G. Keshan P377                         .
OA
DATE:       July 18, 1995
-*EE NIMS --.. Y.~2. -
M_
e PBM 95 0460 M
TO:
K.
R. Anundson P377 W. J. Hennestyy R. D.
Bronk N. L. Hoefert c.
A. Castell P377 FROM:
F. P. Hennessy D.
C. Ryggs M. G. Keshan P377 DATE:
July 18, 1995


==SUBJECT:==
==SUBJECT:==
i USF, OF CARBOEINC PAINr As A PRIMER FOR TME MULTIAssmMBLY STomAss asANNTe                                                                                   E. . ,
USF, OF CARBOEINC PAINr As A PRIMER FOR TME MULTIAssmMBLY STomAss i
REFEARHCE(4) e Eine injection Plant,            in the Primary Systasa at the J. M. Farley Muclear '
asANNTe E..,
by Prince Patton, presanted at the INPO Radiological                           (j Prot ** tion Managgra MorXgnQp play 22-23. 199E                                         "
REFEARHCE(4) e Eine injection in the Primary Systasa at the J. M. Farley Muclear '
An Engineering Assessment of Zine Ad'dition to PWR Primary Coolant                                       ~
Plant, by Prince Patton, presanted at the INPO Radiological (j
by Westinghouse Electric Corporation, SG-94-02-006, February 7'1'99,4Q COPY TO:       M. F. Baumann P377                                                                     --.,-.-
Prot ** tion Managgra MorXgnQp play 22-23. 199E An Engineering Assessment of Zine Ad'dition to PWR Primary Coolant
M. K. Conry A. J. Cayim                   E. D. Schultz                                             C File                           R. E. Soisert                                               ;
~
On July 14,                                                                                               .
by Westinghouse Electric Corporation, SG-94-02-006, February 7'1'99,4Q COPY TO:
Dennis     and Mark had compiled concerning the use of carboxinc spent fuel pool.                                                                     in the paint 1995 Den lead in the carborina  Ourpaint concern stame from the fact that the levels of sino and chemi a1 consamtmation control      are per in excess     of the corresten      levels Alleysi n,s1.etant    allowed in NF 3.1.1 that while it is acceptable to use the two MSBs which have already             its sancludsn been .                      ,
M.
painted with carbozine, we should not use the carbozine in the future unless..i"~"
F.
all surfaces primed with the carbozine paint receive a top coating of epox g i j (We are currently carbozine                in thetopcoat.)
Baumann P377 M. K. Conry C
with an epoxy      process of investigating the leachability of the                --
A. J. Cayim E. D. Schultz File R.
This memo documents our review and analysia.                           .      ,
E.
The carbozinc is used to coat the Multiassembly storage Basket (Nas) which will be innerset in the spent fuel pool. While the carbosino outer                     surface o; I'"                   '
Soisert On July 14, Dennis and Mark had compiled concerning the use of carboxinc paint 1995 Den spent fuel pool.
the HSB is sealed with an epoxy coating, the arboninc on the inner sulface of w the11Man    will be caractly CKDOStd to the acidic anvirnnmans ei r.nh fusi soci . "
Our concern stame from the fact that in the the levels of sino and lead in the carborina paint are in excess of the levels allowed in NF 3.1.1 chemi a1 consamtmation control per corresten n,s1.etant Alleysi that while it its sancludsn is acceptable to use the two MSBs which have already been painted with carbozine, we should not use the carbozine in the future unless..i"~"
                  , ..e.m, it is not intended for inanersion in acidic solutions.z.tseracure to conduct laboratory tests for leachability.                           This statement led us     rrom  '" the manuf    '
all surfaces primed with the carbozine paint receive a top coating of epox g i j (We are currently in the process of investigating the leachability of th carbozine with an epoxy topcoat.)
The tests showed that an               yb uncoated carbozine surface will leach significant               amounts of sinc into' colution No. 55-0130when exposed to simulated spent fuel pool cooling water. Calculation =                                ~
e This memo documents our review and analysia.
iner.ama         estimates that the level of sinc in the spent fuci pool will                               "",~,,
The carbozinc is used to coat the Multiassembly storage Basket will be innerset in the spent fuel pool.
immersed in the spent fuel D001 for at houra.os ppb if th sosal uncontea surface of the c                             -
(Nas) which While the carbosino outer surface o; I'"
2 time in much longer than we would actually expect,wkil.           i t. is A 4s W i===rown would be oubmerged that long.                                             femmible tnat the MSB 7 4
the HSB is sealed with an epoxy coating, the arboninc on the inner sulface of the Man will be caractly CKDOStd to the acidic anvirnnmans ei r.nh f w
                                                                                                                          <O
11,..e.m, usi soci. "
it is not intended for inanersion in acidic solutions.z.tseracure rrom the manuf to conduct laboratory tests for leachability.
This statement led us The tests showed that an b
uncoated carbozine surface will leach significant amounts of sinc into' y
colution when exposed to simulated spent fuel pool cooling water.
=
No. 55-0130 Calculation
~
iner.ama estimates that the level of sinc in the spent fuci pool will immersed in the spent fuel D001 for at houra.os ppb if th sosal uncontea surface of the c
"",~,,
time in much longer than we would actually expect,wkil. A 4s W i===rown 2
i t.
is would be oubmerged that long.
femmible tnat the MSB 7 4
<O


          ----- .                        ..      .- - - . - - . _ , - - - ~                                             _. .,~                                 .      .~. -
.- - -. - -. _, - - - ~
        *Aug-14-96                                                                                                                               ;
_..,~
04:47P P5NP NRC Resident Office                                     414-755-4374
.~. -
                                                                                                                                                            ! 05
*Aug-14-96 04:47P P5NP NRC Resident Office 414-755-4374
! 05
{
{
* M*:=r- - g __
M*:=r.
I PBM 95-0460 i
- - g __
July 10, isss l
I PBM 95-0460 July 10, isss i
v.go a                                                                                                           'J %   ~
v.go a
3
'J %
                                                                                                                                                    . s.
~
The limits neerial    to set   forth in be used                MP 3.1.1 are in terms of contaminantlevels in the '
l 3
itself.
. s.
in materials which are to be used in critical applications suchcinc and lead are limited coolant paist    is system     or the spent fuel pool. The level of sinc in the carbosing'         as the remotor
The limits set forth in MP 3.1.1 are in terms of contaminant neerial to be used itself.
!                      noth matar a a                  while the level of &ead as ggg peu                                                 ,          .
levels in the in materials which are to be used in critical applications suchcinc and lead are limited coolant system or the spent fuel pool. The level of sinc in the carbosing' as the remotor paist is while the level of &ead as ggg peu noth matar a a
]                     stainless steel compartment)eh w&11 he used streetly (ger                         e autrisants nassanc. on aeur peeeeduwe gewes as well as materials which will be used u '-
]
indirectly (for exaspie, cleanaers to be used on a carbon steel comptEre'.M -e.T.
stainless steel compartment)eh w&11 he used streetly (ger nassanc.
,                    which will contac*, secondary coolant which will then contact stainless se ==,
e autrisants on aeur peeeeduwe gewes as well as materials which will be used u '-
indirectly (for exaspie, cleanaers to be used on a carbon steel comptEre'.M
-e which will contac*, secondary coolant which will then contact stainless se
.T.
components).
components).
sine or lead) The limits in the procedure for low melting point metals' (1tuei materials usedare          hosed on indirectly              to direet   eenteess we taelude these limite en be ocaservative,                                                           e f for direct contact,                                                        accause 250 ppe is allowable the 95 ppb sinc level in the spent fuel pool will not be                                                 .
The limits in the procedure for low melting point metals' (1tuei
detrimental spent    fuel pool.to corrosion rates of the apent fuel peel or any ceaponents in cd )
 
                    ._-a._,                 . aThe % lead conoestration      ,n,          le 50 times less than CD9 31DCy, eyonc run pool w&1l Dt insignificant.                               a,_
==,
sine or lead) are hosed on direet eenteess we taelude these limite en f
materials used indirectly to be ocaservative, e
accause 250 ppe is allowable for direct contact, the 95 ppb sinc level in the spent fuel pool will not be detrimental to corrosion rates of the apent fuel peel or any ceaponents in cd )
spent fuel pool.
The lead conoestration le 50 times less than CD9 31DC
._-a._,
. a %
,n, eyonc run pool w&1l Dt insignificant.
y, a,_
pool or in the reactor coolant system. Westinghouse has no specific limits on zine c
_m=:r.
_m=:r.
pool or in the reactor coolant system. Westinghouse has no specific                              e        fuel limits on zine c began injecting zine acetate into the primary,                      In fact, one PWR (Farley) recently4 _sty '-
In fact, one PWR (Farley) recently4 _ y '-
i reduce radiation levels in the primary system (Reference 1). coolant system in order to.g..                                     u !'                     i support the sinc addition at rarisy.                                                       In order to''                                                  '
e fuel began injecting zine acetate into the primary, st reduce radiation levels in the primary system (Reference 1). coolant system in order to.g..u !'
on primary system materials was performed (Reference 2) .an angtneering                                                     a assessmen i
i i
l concluded that; zine levels of 10                                                     The assessmenc Parley injected zine acetate into their primary coolant- 40 ppbsystem months.
In order to''
can actually for nine reduce corrosion rates. -
support the sinc addition at rarisy.
The zinc concentration in their primary coolant 4                the zinc injection was successful at lowering outage dose rateswas = 40 ppb.                                 While ^
on primary system materials was performed (Reference 2).an angtneering assessmen a
thick black scale was discovered on the fuel.                                               , an unusually j
i concluded that; zine levels of 10 The assessmenc l
i conclusively yet    been foune. linked to the sinc injection, an alternate explanation has notWhile this scale has would not                Until the Farley experience is fully evaluated, we eerseialy
Parley injected zine acetate into their primary coolant-40 ppb can actually reduce corrosion rates. -
.                  subject it be willing to introdues sinc into the primary coolant system and                                                     O s
months.
zine borate,to high temperatures and pressure of power operation. However.
system for nine The zinc concentration in their primary coolant the zinc injection was successful at lowering outage dose rateswas = 40 ppb.
I                                                                                                                                             .e soluble at          a possible precipitate in the spent fuel pool water. is m6*chtmor,e*                                                     ,
While ^
.                   temperature room temperature than at elevated temperatures. In fact, at xcca t ...                                                              ,
thick black scale was discovered on the fuel.
borate la           (essentially spent fuel pool temperature),                                                                             *'
4
l which would be eagseated due to teaching foem the unesated Mst.
, an unusually conclusively linked to the sinc injection, an alternate explanation has notWhile this scale has j
!                            Addttionally. Farley injected siac for nine months, whereas the sine                                               S'.h I
yet been foune.
j
Until the Farley experience is fully evaluated, we eerseialy i
;                one month due to removal of the sino by the spent fugl pool dem                                                               v 4
would not be willing to introdues sinc into the primary coolant system and subject it to high temperatures and pressure of power operation.
Therefore, s.han' a.o percent the sDent fuel in the pool will ka suP*=.4 ** the sine for less                                                 *""
O zine borate, s
lower temperatureetand        thereducedtime that             the Farley fuel was. The combination of                         .,
However.
l contact                                                          - - -
I a possible precipitate in the spent fuel pool water. is m6*chtmor,e*
  ;              not with form       on the' carboxinc the uncoated      fuel in theis spent                   fuel pool and that use of the existing Mstime acceptable.                                                           E.'
.e soluble at room temperature than at elevated temperatures.
leads i
temperature borate la (essentially spent fuel pool temperature),
correct,                                                                  To ensure that our conclusions                   % .
In fact, at xcca t...
  ;              transfer tube Addita==a11        ,      to insure that eine ingrese into the RCS is minimitedthe                                             g spe j                                  7 any previsualy irraalataa rual which im                                       ,      .
which would be eagseated due to teaching foem the unesated Addttionally. Farley injected siac for nine months, whereas the sine S'.h l
  .              cpent fuel poS1 will be visually inspected for unusual scale.asape.ed to minc in cne l
Mst.
one month due to removal of the sino by the spent fugl pool dem I
j Therefore, the sDent fuel in the pool will ka suP*=.4 ** the sine for less v
4 s.han' a.o percent et the time that the Farley fuel was. The combination of lower temperature and reduced contact l
not form on the' fuel in the spent fuel pool and that use of the existing Mstime leads with the uncoated carboxinc is acceptable.
E.'
To ensure that our conclusions transfer tube to insure that eine ingrese into the RCS is minimitedthe spe
: correct, i
Addita==a11,
7 any previsualy irraalataa rual which im g
j cpent fuel poS1 will be visually inspected for unusual scale.asape.ed to minc in cne l
i 4
i 4
                                                                                                                                .g4      h     p.
h p.
.g4


                                                                                                  .v ug-1C-C3 OC:47P PSNP NRC Resident Of'f' 1 ce                 C14-755-4374                                 03 (y- s:-:r he
.v ug-1C-C3 OC:47P PSNP NRC Resident Of'f' 1 ce C14-755-4374 03 (y
                                                                                          .N                 f PBM 95-0460                                                               '"
- s:-:r he
July 18, 1925                                                                                     l      l Page 3 f
.N f
                                                                                                    *8   _                ,
PBM 95-0460 July 18, 1925 l
These mitigating motions are sufficient to allow use of the two MSB's whose                   '
Page 3 f
internal surfaces are uncoated carborinc.
*8 These mitigating motions are sufficient to allow use of the two MSB's whose internal surfaces are uncoated carborinc.
carbo 21nc is not acceptable in the lens erua for two reasone.However, use of the uncoated   -              I First, until the.
carbo 21nc is not acceptable in the lens erua for two reasone.However, use of the uncoated scale on the Parley fuel is conclusively emplained, sino atmuld continue to be First, until the.
scale on the Parley fuel is conclusively emplained, sino atmuld continue to be treated 35   ppb as  an of level undesirable sino in thecontaminant whichwill spent fuel pool   should cause beus minimised.Secondly,*a a s.a persens es our spees smet poea M altser, vale resta     to exhaust to mesa                  .-
treated as an undesirable contaminant which should be minimised.
expensive to replace and expensive to dispose of. Additionally, using the will   limit our ability to use that same dominera11 er to Mremove con from the kWST.
35 ppb level of sino in the spent fuel pool will cause us Secondly,*a a s.a persens es our spees smet poea M altser, vale resta to mesa to exhaust expensive to replace and expensive to dispose of. Additionally, using the will limit our ability to use that same dominera11 er to remove co from the kWST.
Coating all carboxino surfaces with epoxy or finding a # .s . J suitable     alternative   primer will allow um to eliminate this logistical prob and extend the life of our domine.
Coating all carboxino surfaces with epoxy or finding a #
4 1'em 4,*A 4
M suitable alternative primer will allow um to eliminate this logistical prob 1'e
                                                                                                                  )
.s. J and extend the life of our domine.
4 4,*A 4)
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      *AU0-14-96 04:46P PBNP NRC Resident Office                                                               414-755-4374 a
*AU0-14-96 04:46P PBNP NRC Resident Office 414-755-4374
                                                                                                                                                    . a. uds +L OZ
. a. uds +L OZ a
                                                                                                                                              ' ***WI'* %
' ***WI'* %
Nuclear Power BusinessMnit                                                               *          '
Nuclear Power BusinessMnit Route Original to S.i.t.
Route Original to S.i.t.
J Report #
Report #                       96-311
96-311
_QAS to copy: ~.S  J             moha-J          '
~.S
(assigned by QAS)                       WORK MONITORINC RF' PORT J. Paltner. E. Schultre%o/h                     i T. Jessessky, J. "Thot/crscri' '
_QAS to copy:
P!le: Ql.1.I g ver: Sean P. McGinty                           Date: 5/22/95       Shift: 1                 L.ocation of Activity: PAB Truck Access fwnnrnminarian A res Group Observed                     Work Document (s)                   Functional Area                                                                                 j Observation Program:
J moha-(assigned by QAS)
Process #
WORK MONITORINC RF' PORT J. Paltner. E. Schultre%o/h i
T. Jessessky, J. "Thot/crscri' '
P!le: Ql.1.I g ver: Sean P. McGinty Date: 5/22/95 Shift: 1 L.ocation of Activity: PAB Truck Access fwnnrnminarian A res Group Observed Work Document (s)
Functional Area Observation Program:
j Process #
Oroup Job Observation (GJO)
Oroup Job Observation (GJO)
MTN                                 WO # 9604669                                                                                                                 ..
MTN WO # 9604669 Mansaement Job Observation (MJ0).
Mansaement Job Observation (MJ0) .                  .
Other hP.7 Part 6 L98 Work Monitoring Report (WMR)h u:tiviry(s) Observed:
Other hP.7 Part 6                           L98             Work Monitoring Report (WMR)h u:tiviry(s) Observed:
Nelding the ahiald lid during the second MSB loading.
2      :
2 ed Le arks:
Nelding the ahiald lid during the second MSB loading.                                                                                                     .    .:
: Romarts showd peio, oeias for *=a senerna.aritum ram:4 aies
Le arks:                 : Romarts showd peio, oeias for *=a senerna .aritum ram:4 aies ed            .
.)
                                                                                            .)
[.{
L2. G.5) At the beginning of my shift, Malatenance had installed the automatic welding rig and laserted the sinms around'tfiMdlEld lid.
L2. G.5) At the beginning of my shift, Malatenance had installed the automatic welding rig and laserted the sinms around'tfiMdlEld lid.
[.{
The welders bcEan by verifying the proper centering of the welding rig relative to the ID of the MSB. They also verifiedih@rrect witch lincup on the welding machine. Although they did not have a procedure that specified this switch lineup, they set up'.tjic ma' chine crrectly based on their knowledge of the process and then verified it by consulting with the welding engineer. After thes8c ecks they l
The welders bcEan by verifying the proper centering of the welding rig relative to the ID of the MSB. They also verifiedih@rrect witch lincup on the welding machine. Although they did not have a procedure that specified this switch lineup, they set up'.tjic ma' chine crrectly based on their knowledge of the process and then verified it by consulting with the welding engineer. After thes8c ecks they                                       l aantured an are on tha MSD and timed the travel of the welding rig through the arc to verify proper torch travel speed. ThedeIorted                           I           a  l
aantured an are on tha MSD and timed the travel of the welding rig through the arc to verify proper torch travel speed. ThedeIorted a I
  -n:asured speed sli           6 htly less than twenty inches per minute. Based on this speed the welding engineer told them to set their voltage to 31
-n:asured speed sli htly less than twenty inches per minute. Based on this speed the welding engineer told them to set their voltage to 31 6
' olts sad n observe a cu Tent limit of 350 amps. The welding engineer had this information on a hand written note which he had nrr -d from a verified table availabic in (bc welder's toolbox with tbc welding procedurcs. The wcldcrs then welded a test bcad y
' olts sad n observe a cu Tent limit of 350 amps. The welding engineer had this information on a hand written note which he had nrr -d from a verified table availabic in (bc welder's toolbox with tbc welding procedurcs. The wcldcrs then welded a test bcad y
stely ten inches long on a test coupon placed on top of the shield lid. All of their equipment operated properly within the
stely ten inches long on a test coupon placed on top of the shield lid. All of their equipment operated properly within the
. eqw .. parameters during this test.
. eqw.. parameters during this test.
  .2) Tbc welders used the automatic welding snachine to place tack welds about two inches long at each or the eightjo;nts where the birn segments met. Once they finished the tack welds, the welders used a pair of pilers to break off the taba that held the shims in place.                                   ,
.2) Tbc welders used the automatic welding snachine to place tack welds about two inches long at each or the eightjo;nts where the birn segments met. Once they finished the tack welds, the welders used a pair of pilers to break off the taba that held the shims in place.
  .2, 5.2,15.3) With the shima securely in ptsee to serve as a backing ring, the two welders set up the welding machine for the root pass.
.2, 5.2,15.3) With the shima securely in ptsee to serve as a backing ring, the two welders set up the welding machine for the root pass.
They began the pass at about the 180* position. As they started the pass. the current rose to approximately 360 ampsgThe welder perrting the welding machine immediately recogniz.ed that he had exceeded his allowable cutTent and adjusted it to.3 Lamps.~~This took ive or six seconds and resulted in an area of tbc weld that had noticeable porosity. Maintenance documented this nocconprmance o_n CR
They began the pass at about the 180* position. As they started the pass. the current rose to approximately 360 ampsgThe welder perrting the welding machine immediately recogniz.ed that he had exceeded his allowable cutTent and adjusted it to.3 Lamps.~~This took ive or six seconds and resulted in an area of tbc weld that had noticeable porosity. Maintenance documented this nocconprmance o_n CR
. 6-357. After completing the weld pass, one of the welders removed this area of the weld with a band grinder. This welder re,r--c-to so welding enginect that he observed a flame under the Srinding wheel which went out when he stopped grinding. The welders -
. 6-357. After completing the weld pass, one of the welders removed this area of the weld with a band grinder. This welder re,r--c-to so welding enginect that he observed a flame under the Srinding wheel which went out when he stopped grinding. The welders -
oncluded that residual solvent from c! caning and decontaminating the MSB caused the flame and resumed work. The observer                                           ide te deenmmination area could not see the name because the MTC and MSD shell blocked thelt line of sight, After grindinr f' reldcd ever this acetion using the automatic welding machine.
oncluded that residual solvent from c! caning and decontaminating the MSB caused the flame and resumed work. The observer ide te deenmmination area could not see the name because the MTC and MSD shell blocked thelt line of sight, After grindinr f' reldcd ever this acetion using the automatic welding machine.
  .2) Foll: wing NDE of the root pas, the welders finished welding the shield lid using three passes with the automatic weldin inchine.
.2) Foll: wing NDE of the root pas, the welders finished welding the shield lid using three passes with the automatic weldin inchine.
They remitned whhin their required parameters throuF.hout these passes.
They remitned whhin their required parameters throuF.hout these passes.
:ey Words: (Key words or phrans so be emered imo WMR database for word scarch.)                                                                         - -
:ey Words: (Key words or phrans so be emered imo WMR database for word scarch.)
SFSI, MSB. Welding. CR 96-357. S-P-96-02                                                                                                             #-
SFSI, MSB. Welding. CR 96-357. S-P-96-02 tecrptable Attributes Deficient Attributes:
tecrptable Attributes                                                                   Deficient Attributes:                                             g,
g,
  .3 Exceptional terrormance:
.3 Exceptional terrormance:
1.0 hiinor. Quicidr Corrected Ifems
1.0 hiinor. Quicidr Corrected Ifems
  .0 Fully Acceptable: G .3, 2.2.15.3                                                     3.0 Less Significant Deficiency:
.0 Fully Acceptable: G.3, 2.2.15.3 3.0 Less Significant Deficiency:
(CR/QCR Generation Necessary) 5.2
(CR/QCR Generation Necessary) 5.2
  .I               inally Acceptable:                                                   4.0 Significant Deficiency:
.I inally Acceptable:
_                                                                                  (CR/QCR Generation Neceasary)
4.0 Significant Deficiency:
_8F-1500, _                                                                                                                                   .
(CR/QCR Generation Neceasary)
E y
E
                                                                                                                                              =L t,gpg
_8F-1500, _
y
=L t,gpg


eAug 14-DO 04:40P PONP NRC Re:m i de nt Office                                                               414-705-4374
eAug 14-DO 04:40P PONP NRC Re:m i de nt Office 414-705-4374 uE.03
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B.3 Job Cuordinsuos R.3 Contaminadon Coatrois               -M yd.jp @ _g_c                     - ;9 11.3 Test Evaluarnoa Q.4 Parts Aratiabtilry                       R.4 RWP Adhersece                         2.1 Wortier Quettiy 5.3 Joh Pre-Sanging                                                                                                                 II.4 Tcas Qualiracesion              **""
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        .      .        Chandstry;   ; n,     R.6 A 4.tiver" t                         2.3 Treintog C.! Sample Points A.Pyy****ECpahel' .h4c.r,. .c             .
li Jfuting R.1 Surveys 1.2 Independeaca 11.2To.e %,
R.7 A! ARA                               2.4 QA Requittments C.2 L4 Pracetces 12.3 Callhfasion               ,a.
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                                              ' K.8 Kadwasan Reduction                 ',
B.3 Job Cuordinsuos R.3 Contaminadon Coatrois
T'.7 Design Coottolia..
-M yd.jp @ _g_c
C.3 Chendcal Control                                 N.CM;. + ''                                                                   12TCalibra@7 3.1 A~fn~_9n                                 dy @ h". W ''''''                                     " -
- ;9 11.3 Test Evaluarnoa Q.4 Parts Aratiabtilry R.4 RWP Adhersece 2.1 Wortier Quettiy II.4 Tcas Qualiracesion 5.3 Joh Pre-Sanging R.5 Accesa curarol 2.2 Craf'-. M 11.6 Poes Maisseanace Tesana Chandstry;
C.4 Clsendci Conaut Program                 S.1 Post. Manning                         3.2 Design %
; n, R.6 A 4.tiver" t 2.3 Treintog A.Pyy****ECpahel'.h4c.r,..c C.! Sample Points R.7 A! ARA 2.4 QA Requittments 12.3 Callhfasion
Eamergemey Pins.f. vy.,     3.2 accurley $quipmem                   3.3 Teseovery Modificesions 13.1 l' " _                  QT i
,a.
13.2 Sassage                         '''    .
C.2 L4 Pracetces
* El n,s. Cimirmanon                           t.2 Ingr.as Con I                       2.4 Dwign       r eering L2.3 ~ ;; N                           ,.
' K.8 Kadwasan Reduction T'.7 Design Coottolia..
tL2 Off-Sisc insirfac.o                     !!.J Eacnri Dudes                       p.      g.--nurDec.IContralf               -
12TCalibra@7 C.3 Chendcal Control N.CM;. + ''
( y;;, lapptpUgp/QDCnla                         .:3 C.3 Drill Lemie.                           E.6 v.bese C       ar.4                   4.1 5%,.t"*6                                 14' A 18u'reemen Besu Co,neri.e E.4 Drtil Crtrique                                   ";InduatdalSafetylc             4.2 CGI fWoon                                 14.2 Equipsment IsonanonT_.'.                                   l Fire Prntactica           T. ) I!ossdag/ Rigging                                                                                                                                   j 4.3 D~ .~ntation Requirernents F.I Combumble Sanrage                                                                                                              14.3 Operat on S-sev h. .j-T.2 Environmental CondJoons               44 Record Storage
3.1 A~fn~_9n dy @ h". W ''''''
                                                                                                                                                                                                        \
C.4 Clsendci Conaut Program S.1 Post. Manning 3.2 Design %
                                                                                                                                    -i.~TihCaEdloon~ Reports .
13.1 l' " _
* l E3 Emergency Ligbung                       T.3 Warning Donca
QT Eamergemey Pins.f. vy.,
                                                                                                      ', tut / Proc /Drwg H.                                                                           i 15.1 Norconformances locnofled E3 FP Equ'pasons laepsea.an                 T.4 Proa.caive Equipmani/Ue3Be i
3.2 accurley $quipmem 3.3 Teseovery Modificesions 13.2 Sassage i
5.1 Work'Insw/pme/Drwg Adequacy               15.2 Cond.tions beefwd .-
El n,s. Cimirmanon t.2 Ingr.as Con I 2.4 Dwign eering L2.3 ~ ;; N r
8.4 Igrunin Control Ponrus                                                                                                                                                                           j 13 Scaffolding /1.addcri                 5.2 Wmk Instr /Prnc/Drwg Adhererrs           !$.3 Conddions Ducurnrnted 1.3         Watcli                       T.6 Confined Space                                     Doc         t Concret -         15.4 herns Segregated
tL2 Off-Sisc insirfac.o
                  ,ctner Penetranons         T.7 Posmans of People                     6.1 Work Instr /ProuDrwg Approval             15.5 CRs Disposinoped
!!.J Eacnri Dudes g.--nurDec.IContralf
                      . General.             T.8 Tools & Equapmsa                     6.2 Work lasta/ Proc /Drwg Control                     -dCecrective Actions a
- ( y;;, lapptpUgp/QDCnla
, 3.1 Commumcanons                           T.9 Rencoens of People                   6.4 Dncumera c'-.           Corumi           16.1 Timely Responses 3.2 Managenunt Oversight                   T.10 Electncal                           6.7 Tempnrery Prncedure Comrol               10.2 Treading 13 Work Planrung
.:3 p.
* T.!L Fall Protecoun                       6.8 Work Closcout Documentanon               16.3 Acdon Prevent Recurrence 14 PrsJob linefang                                       . Rad Waste ~                           Material Centrol               16.4 Response Adequacy 7,
C.3 Drill Lemie.
. 3.5 Self.Checlung                           W.I Stupping Papers                                                                                             ~
E.6 v.bese C ar.4 4.1 5%,.t"*6 14' A 18u'reemen Besu Co,neri.e E.4 Drtil Crtrique
7.1 Recerpe Contros                                     -f 3 6 ladependens Venfesanun QA RecordU - p W 2 Stuppens Voksne Consa.nor             7.2 Hoede-M                                   87.4 Reensda casnotees             -
";InduatdalSafetylc 4.2 CGI fWoon 14.2 Equipsment IsonanonT_.'.
  ),7 Shaft Relief /Tu...       e w.3 Tra-, .- ; vesusee                             80 e Ceneest of Pfoseriel'           17.2 RestfW Omftgg 3.0 Loghecptng/Re ore                                 It nerisome M tertal           8.1 Maional Trooe htiny                                   { ( Audiu -                           '
l Fire Prntactica T. ) I!ossdag/ Rigging 4.3 D~.~ntation Requirernents 14.3 Operat on S-sev h..j-j F.I Combumble Sanrage T.2 Environmental CondJoons 44 Record Storage
1.9 Comma:x!/Connel                         4.1 So!!! Kits                           5.2 Matena! T11gmg
-i.~TihCaEdloon~ Reports.
- ).lU supervisory lavonemeff                 T. 2 Protecave Claming 18.1 Audit ?he''ule                Q c DDPC3IIT0Cc33t3 W '               1R.2 AQCQUACy of AIM 11U **'
l
3 il Concuirm Checks                       2.3 Eye Wash                             9.1 Personnel Qualificanon                     18.3 Atidit Cheeksist Use *G I 12 Puudub Dnering                         Z.4 Asbestos Corurol                                                                                                                         ''
\\
9.2 Procedure Quahficauon                               . General Operatio~ns -
E3 Emergency Ligbung T.3 Warning Donca
Plant Canditnans .         Z.5 Gas Botde Storage                   9.3 Weld laspeedon                                                           ~ '*
', tut / Proc /Drwg H.
X.! Other                                   ..
15.1 Norconformances locnofled i
  '.! Equipmt N Conditiert                   Z.0 CES System                                                                                                                 "'
E3 FP Equ'pasons laepsea.an T.4 Proa.caive Equipmani/Ue3Be 5.1 Work'Insw/pme/Drwg Adequacy 15.2 Cond.tions beefwd.-
                                                                                              ,          ' Inspect!aas _.
i j
t2 Hnuactecen5                                                                        10.1 la2postor IM7 :asence                         -
8.4 Igrunin Control Ponrus 13 Scaffolding /1.addcri 5.2 Wmk Instr /Prnc/Drwg Adhererrs
_ w      .-
!$.3 Conddions Ducurnrnted 1.3 Watcli T.6 Confined Space Doc t Concret -
l' 3 P'vit Praccces                                                                     10.2 Inspecuans spectned
15.4 herns Segregated
!'s Scistruc Storme                                                                     10.31nspector QuaJ1ftcanons I-
,ctner Penetranons T.7 Posmans of People 6.1 Work Instr /ProuDrwg Approval 15.5 CRs Disposinoped
  '.'          Rescration 10 4 Acceptance 1irruts l
. General.
10.5 QC 1- p- tion l
T.8 Tools & Equapmsa 6.2 Work lasta/ Proc /Drwg Control
-dCecrective Actions a
, 3.1 Commumcanons T.9 Rencoens of People 6.4 Dncumera c'-.
Corumi 16.1 Timely Responses 3.2 Managenunt Oversight T.10 Electncal 6.7 Tempnrery Prncedure Comrol 10.2 Treading 13 Work Planrung T.!L Fall Protecoun 6.8 Work Closcout Documentanon 16.3 Acdon Prevent Recurrence 14 PrsJob linefang
. Rad Waste ~
Material Centrol 16.4 Response Adequacy 7,
. 3.5 Self.Checlung W.I Stupping Papers 7.1 Recerpe Contros
-f QA RecordU - p
~
3 6 ladependens Venfesanun W 2 Stuppens Voksne Consa.nor 7.2 Hoede-M 87.4 Reensda casnotees
),7 Shaft Relief /Tu...
e w.3 Tra-,.- ; vesusee 80 e Ceneest of Pfoseriel' 17.2 RestfW Omftgg 3.0 Loghecptng/Re ore It nerisome M tertal 8.1 Maional Trooe htiny
{ ( Audiu -
1.9 Comma:x!/Connel 4.1 So!!! Kits 5.2 Matena! T11gmg 18.1 Audit ?he''ule Q
- ).lU supervisory lavonemeff T. 2 Protecave Claming c DDPC3IIT0Cc33t3 W '
1R.2 AQCQUACy of AIM 11U **'
3 il Concuirm Checks 2.3 Eye Wash 9.1 Personnel Qualificanon 18.3 Atidit Cheeksist Use *G I 12 Puudub Dnering Z.4 Asbestos Corurol 9.2 Procedure Quahficauon
. General Operatio~ns -
Plant Canditnans.
Z.5 Gas Botde Storage 9.3 Weld laspeedon X.! Other
~ '*
'.! Equipmt N Conditiert Z.0 CES System t2 Hnuactecen5
' Inspect!aas _.
_ w 10.1 la2postor IM7 :asence l' 3 P'vit Praccces 10.2 Inspecuans spectned
!'s Scistruc Storme I-10.31nspector QuaJ1ftcanons Rescration 10 4 Acceptance 1irruts l
10.5 QC 1-p- tion l
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WISCONSID EleCfnC                   Post 4t' Fax Note 7671          h^~ h    '9 a wisconsin entnarcowaur      _
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blyJiHMim h^~ h WISCONSID EleCfnC Post 4t' Fax Note
From: Mary Carpenter May 28,1996                                                                                 !
'9 7671 u g 9ggon
Wisconsin Electric suspends loading of spent fuel containers
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after combustible gas causes brief gas burn TWO CREEKG, Wis. - Loading of spent nuclear fuelinto dry storage containers was suspended at Point Beach Nuclear Plant after combustible gas was detected and caused a brief gas burn during a welding procedure early this mornin0 Fuel assemblies had been placed into a container and removed from the spent fuel pool. While a shield lid was being mechanically welded to the top of the container, combustible gas was detected and a brief gas burn occurred. Point Beach employees diccontinued the welding procedure. No one was injured and there was no risk to the general public. The occurrence did not result in any release of radiation.
From: Mary Carpenter May 28,1996 Wisconsin Electric suspends loading of spent fuel containers after combustible gas causes brief gas burn TWO CREEKG, Wis. - Loading of spent nuclear fuelinto dry storage containers was suspended at Point Beach Nuclear Plant after combustible gas was detected and caused a brief gas burn during a welding procedure early this mornin0 Fuel assemblies had been placed into a container and removed from the spent fuel pool. While a shield lid was being mechanically welded to the top of the container, combustible gas was detected and a brief gas burn occurred. Point Beach employees diccontinued the welding procedure. No one was injured and there was no risk to the general public. The occurrence did not result in any release of radiation.
          *We are conducting a thorough investigation and we will not resume loading spent fuel until we have a clear understanding of the cause of the gas bum," ocid                   '
*We are conducting a thorough investigation and we will not resume loading spent fuel until we have a clear understanding of the cause of the gas bum," ocid Bob Link, vice president of nuclear power for Wisconsin Electric. "We will thoroughly review all of the related information to determine the root cause of this mornin0's occurmnca.'
Bob Link, vice president of nuclear power for Wisconsin Electric. "We will thoroughly review all of the related information to determine the root cause of this mornin0's occurmnca.'
Plant employees previuusly luaded two containers successfully, one as decently as last week using the same loading process. These containers are now located at the dry cask storage facility on the plant site.
Plant employees previuusly luaded two containers successfully, one as decently as last week using the same loading process. These containers are now located at the dry cask storage facility on the plant site.                               -
Spent fuel has been safely managed at Point Beach since the plant went into operation in 1970. However, the spent fuel storage poolinside the plant is becoming full, and additional storage capacity is necessary for the continued operation of the plant.
Spent fuel has been safely managed at Point Beach since the plant went into operation in 1970. However, the spent fuel storage poolinside the plant is becoming full, and additional storage capacity is necessary for the continued operation of the plant.
Wisconsin Electric Power Co., a subsidiary of Wisconsin Energy Corp., provides electn*c natural gas and/or steam service to about 2.3 million people in snuthenstem Wiscansin (including the Milwaukee ama), the Appleton nmn, the Prairie du Chien area, and portions of northeastern Wisconsin and Michigan's Upper Perrinsule.
Wisconsin Electric Power Co., a subsidiary of Wisconsin Energy Corp., provides electn*c natural gas and/or steam service to about 2.3 million people in snuthenstem Wiscansin (including the Milwaukee ama), the Appleton nmn, the Prairie du Chien area, and portions of northeastern Wisconsin and Michigan's Upper Perrinsule.
Line 785: Line 1,016:


l May 28, 1996 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PN0-III-96-033 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by Region III staff (Lisle, Illinois) on this date.
l May 28, 1996 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PN0-III-96-033 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by Region III staff (Lisle, Illinois) on this date.
Facility                                     Licensee Emergency Classification Wisconsin Electric Power Co.                   Notification of Unusual Event Point Beach 1 2                                 Alert Two Rivers, Wisconsin                           Site Area Emergency Dockets: 50-266,50-301                           General Emergency X Not Applicable
Facility Licensee Emergency Classification Wisconsin Electric Power Co.
Notification of Unusual Event Point Beach 1 2 Alert Two Rivers, Wisconsin Site Area Emergency Dockets: 50-266,50-301 General Emergency X Not Applicable


==Subject:==
==Subject:==
UNIDENTIFIED GAS IGNITED DURING SPENT FUEL CASK WELDING At 2:45 a.m. (CDT) on May 28, 1996, an unidentified gas ignited inside a dry cask spent fuel storage container during initiation of welding the shield lid inside the container. The container had been loaded with spent fuel and removed from the spent fuel storage pool. The gas ignition, which was heard and observed by plant technicians, displaced the shield lid, leaving it in place but tipped at a slight angle -- with one edge about 1 inch higher than normal. The shield lid is 9 inches thick and weighs about 4,400 pounds.                  .
UNIDENTIFIED GAS IGNITED DURING SPENT FUEL CASK WELDING At 2:45 a.m. (CDT) on May 28, 1996, an unidentified gas ignited inside a dry cask spent fuel storage container during initiation of welding the shield lid inside the container. The container had been loaded with spent fuel and removed from the spent fuel storage pool. The gas ignition, which was heard and observed by plant technicians, displaced the shield lid, leaving it in place but tipped at a slight angle -- with one edge about 1 inch higher than normal. The shield lid is 9 inches thick and weighs about 4,400 pounds.
The VSC-24 cask was removed from the spent fuel storage pool about 4:10 p.m. on May 27 and placed in the cask decontamination area in the auxiliary building. The cask remained filled with water, and about 30 gallons was removed to create an air space under the shield lid. A welding machine is used to weld the shield lid in place. The gaseous ignition occurred during initiation of welding, but before any welding took place.
The VSC-24 cask was removed from the spent fuel storage pool about 4:10 p.m. on May 27 and placed in the cask decontamination area in the auxiliary building. The cask remained filled with water, and about 30 gallons was removed to create an air space under the shield lid. A welding machine is used to weld the shield lid in place. The gaseous ignition occurred during initiation of welding, but before any welding took place.
There was no evidence of any damage to the spent fuel in the cask qs a result of the gaseous ignition. ContinuoJs air measurements in the cask decontamination area showed no measurable radioactivity. There were no injuries.
There was no evidence of any damage to the spent fuel in the cask qs a result of the gaseous ignition. ContinuoJs air measurements in the cask decontamination area showed no measurable radioactivity. There were no injuries.
The licensee is investigating the incident and is attempting to identify the gas which ignited. After a preliminary investigation, the licensee plans to return the cask to the spent fuel storage pool for further examination. The licensee is continuing to monitor for radioactivity and combustible gases.
The licensee is investigating the incident and is attempting to identify the gas which ignited. After a preliminary investigation, the licensee plans to return the cask to the spent fuel storage pool for further examination. The licensee is continuing to monitor for radioactivity and combustible gases.
The NRC senior resident inspector responded to the plant site after being notified of the event and is continuing to monitor the licensee's activities. Additional inspectors are being sent to the site from the regional office.
The NRC senior resident inspector responded to the plant site after being notified of the event and is continuing to monitor the licensee's activities. Additional inspectors are being sent to the site from the regional office.
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  . _ . _ _ . _ .  . ~ _ . . _ . . . . = _ _ . _ _ _ . . _ _ _ . _ _ . . . . _ _ _ - . _ - . _ .             . . . _ _ . _ _ _ . _ . . . __
. ~ _
I                 PNG-Ill-96-033                                                                 !
.. _.... = _ _. _ _ _.. _ _ _. _ _.... _ _ _ -. _ -. _.
I PNG-Ill-96-033 !
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This is the third VSC-24 cask loaded by the licensee. The other two casks have been placed on the outdoor storage pad. Each cask holds 24 fuel assemblies, l
This is the third VSC-24 cask loaded by the licensee. The other two casks have been placed on the outdoor storage pad. Each cask holds 24 fuel assemblies, l
The-licensee plans to issue a news release. The State of Wisconsin will be notified. The information in this preliminary notification has been
The-licensee plans to issue a news release. The State of Wisconsin will be notified. The information in this preliminary notification has been
                  -reviewed with licensee management.
-reviewed with licensee management.
Region III (Chicago) was notified of this event by the resident inspector at 3:40 a.m. on May 28, 1996. This information is current as of 10 a.m.
Region III (Chicago) was notified of this event by the resident inspector at 3:40 a.m. on May 28, 1996. This information is current as of 10 a.m.
on May 28, 1996.
on May 28, 1996.


==Contact:==
==Contact:==
TIMOTHY K08TEZ                                             MARTIN FARBER (414)755-2309                                               (708)829-9605 4
TIMOTHY K08TEZ MARTIN FARBER (414)755-2309 (708)829-9605 4
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                        "'8 UNITED STATES
"'8 UNITED STATES NUCt. EAR REGUL.$.'ORY COMMISSION
[                                    NUCt. EAR REGUL.$.'ORY COMMISSION
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5, sos wannENwuE ROAD g                                           ustE. K.UNotS 80632-4355 May 29, 1996 MEMORANDUM To:           Roy J. Caniano, Team Leader
5, sos wannENwuE ROAD g
                                            . Augmented Inspection Team (AIT)
ustE. K.UNotS 80632-4355 May 29, 1996 MEMORANDUM To:
Roy J. Caniano, Team Leader
. Augmented Inspection Team (AIT)
Point Beach Nuclear Plant FROM:
Point Beach Nuclear Plant FROM:
John A. Grobe, Deputy Directo Division of Reactor Safety
John A. Grobe, Deputy Directo Division of Reactor Safety


==SUBJECT:==
==SUBJECT:==
AIT CHARTER FOR POINT BEACH DRY CASK EVENT On May 28, 1996, a gas ignition event occurred during dry cask activities at the Point Beach Nuclear Plant. Based on discussions with the Offices of Nuclear Reactor Regulation, Nuclear Materials Safety and Safeguards, and Analysis and Evaluation of Operational Data, and on initial inspection findings regarding the event, an AIT has been chartered in accordance with NRC Inspection Manual Chapter 0325 (e.g., significant or unexpected system interaction).
AIT CHARTER FOR POINT BEACH DRY CASK EVENT On May 28, 1996, a gas ignition event occurred during dry cask activities at the Point Beach Nuclear Plant. Based on discussions with the Offices of Nuclear Reactor Regulation, Nuclear Materials Safety and Safeguards, and Analysis and Evaluation of Operational Data, and on initial inspection findings regarding the event, an AIT has been chartered in accordance with NRC Inspection Manual Chapter 0325 (e.g., significant or unexpected system interaction).
i Attached for your implementation is an AIT Charter for the inspection of the dry cask gas ignition event of May 28 at Point Beach. The objectives of the team are to identify and communicate both'the facts of the event and any generic   safety concerns, and to document the findings and conclusions of the onsite inspection.
Attached for your implementation is an AIT Charter for the inspection of the i
dry cask gas ignition event of May 28 at Point Beach.
The objectives of the team are to identify and communicate both'the facts of the event and any generic safety concerns, and to document the findings and conclusions of the onsite inspection.
Should you have any questions regarding these objectives or the attached Charter, please do not hesitate to contact me.
Should you have any questions regarding these objectives or the attached Charter, please do not hesitate to contact me.


==Attachment:==
==Attachment:==
AIT Charter cc w/att:         J.-M. Taylor, EDO                     G. H. Marcus, NRR J. L. Hilhoan, OEDO                   C. J. Paperiello, NMSS H. L. Thompson, OEDO                 W. O. Travers, NMSS H. J. Miller, RIII                   C. J. Haughney, NMSS A. B. Beach, RIII                     E. J. Leeds, NMSS W. L. Axelson, RIII                   E. L. Jordan, AEOD l
AIT Charter cc w/att:
G. E. Grant, RIII                       R. J. Barrett, AE00 C. D. Pederson, RIII                   8. C. McCabe, OEDO W. T. Russell, NRR                     A. J. Kugler, LPM /NRR R. E. Zimmeman, NRR                     A. G. Hansen, LPM /NRR J. W. Roe, NRR                         T. J. Kobetz, SRI
J.-M. Taylor, EDO G. H. Marcus, NRR J. L. Hilhoan, OEDO C. J. Paperiello, NMSS H. L. Thompson, OEDO W. O. Travers, NMSS H. J. Miller, RIII C. J. Haughney, NMSS A. B. Beach, RIII E. J. Leeds, NMSS W. L. Axelson, RIII E. L. Jordan, AEOD l
      % D i uv^i4 4/.
G. E. Grant, RIII R. J. Barrett, AE00 C. D. Pederson, RIII
: 8. C. McCabe, OEDO W. T. Russell, NRR A. J. Kugler, LPM /NRR R. E. Zimmeman, NRR A. G. Hansen, LPM /NRR J. W. Roe, NRR T. J. Kobetz, SRI
% D i uv^i4 4/.


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    .FROM'; Panasonic PPF l
.FROM'; Panasonic PPF Auomented Insnection Team Charter - Point Beach Nuclear Plant l
Auomented Insnection Team Charter - Point Beach Nuclear Plant                                       ,
Examine the circumstances surrounding the dry cask ignition event at the Point Beach Nuclear Plant on May i
Examine the circumstances surrounding the dry cask ignition event at the Point Beach Nuclear Plant on May 28, 1996, including but not limited to the                                             i following:
28, 1996, including but not limited to the following:
1.
1.
Develop and validate a chronological sequence of events and activities for the dry cask evolution, detailing events just prior to and immediately after the gas ignition.
Develop and validate a chronological sequence of events and activities for the dry cask evolution, detailing events just prior to and immediately after the gas ignition.
2.
2.
Compare this sequence of events to other dry cask loading evolutions at load. Beach to identify any anomalies associated with this particular Point 3.
Compare this sequence of events to other dry cask loading evolutions at Point Beach to identify any anomalies associated with this particular load.
3.
Evaluate the licensee's actions during and followin the event; including their immediate response to the event, is lementation of emergency plans and management response. procedures, event reporting, fo lowup actions, and 4.
Evaluate the licensee's actions during and followin the event; including their immediate response to the event, is lementation of emergency plans and management response. procedures, event reporting, fo lowup actions, and 4.
Evaluate the extent of the licensee's analysis and determination of the root cause for the event, including potential source (s) of hydrogen generation, actions.
Evaluate the extent of the licensee's analysis and determination of the root cause for the event, including potential source (s) of hydrogen generation, and the initial evaluation of appropriate corrective actions.
and the initial evaluation of appropriate corrective 5.
5.
Determine if appropriate attention was given to the condition of systems and components associated with dry cask evolutions, including compatibility of the dry cask with spent fuel pool conditions.
Determine if appropriate attention was given to the condition of systems and components associated with dry cask evolutions, including compatibility of the dry cask with spent fuel pool conditions.
I
I 6.
: 6.     Determine any potential generic implications of the event. Evaluate the technical' support by the vendor for the prevention of similar events.                                         :
Determine any potential generic implications of the event.
Evaluate the technical' support by the vendor for the prevention of similar events.
7.
7.
Evaluate the adequacy and appropriateness of radiation protection.
Evaluate the adequacy and appropriateness of radiation protection.
precautions activity.        taken by the licensee as part of the dry cask loading 8.
precautions taken by the licensee as part of the dry cask loading activity.
8.
Evaluate the radiation protection consequences of the event to both the plant staff and the general public.
Evaluate the radiation protection consequences of the event to both the plant staff and the general public.
i I
i I
i
i


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    '.      .                                                                                                  uno-   '
;4 INTERNAL i
;4                                                                                                               .
CORRESPONDENCE e
i INTERNAL e
PBM 96-0320 To: C. A. Castell B. D. O'Connell S. A. Pfaff S. J. Zepplin
CORRESPONDENCE PBM 96-0320 To: C. A. Castell             B. D. O'Connell S. A. Pfaff S. J. Zepplin
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Frean:   G. J. Maxfield 4
Frean:
Date: May 29,1996 3            
G. J. Maxfield 4
Date: May 29,1996 3


==Subject:==
==Subject:==
INCIDENTINVESTIGATIONII 96-01 BRIEF COMBUSTIBLE GAS BURN DURING DRY STORAGE CONTAINER SHIFTD LID WELDING i             Copy To: R. E. Link W. B. Fromm         T. C. Guay     G. J. Maxfield j                       J. G. Schweitzer     R. D. Seizert       T7A.3 i
INCIDENTINVESTIGATIONII 96-01 BRIEF COMBUSTIBLE GAS BURN DURING DRY STORAGE CONTAINER SHIFTD LID WELDING i
At approximately 0245 hours on Monday, May 28,1996, during initiation ofwelding the shield l
Copy To: R. E. Link W. B. Fromm T. C. Guay G. J. Maxfield j
lid inside the third dry fuel storage container, an unidentified combustible gas briefly igni 3          ignition slightly cocked the shield lid. Continuous air measurements in the cask decontaminat area showed no measurable radioactivity. There were no personnelinjuries as a result of this event. An initial activity plan focused on notification of the NRC resident inspector;
J. G. Schweitzer R. D. Seizert T7A.3 At approximately 0245 hours on Monday, May 28,1996, during initiation ofwelding the shield i
;i determination ofimmediate reporting requirements; identification and monitoring of the source               ,
lid inside the third dry fuel storage container, an unidentified combustible gas briefly igni l
l d
ignition slightly cocked the shield lid. Continuous air measurements in the cask decontaminat 3
the gas; removal of the shims and replacement of the shield lid; and preparations for re loaded container to the spent fuel pool                                                                     '
area showed no measurable radioactivity. There were no personnelinjuries as a result of this event. An initial activity plan focused on notification of the NRC resident inspector; determination ofimmediate reporting requirements; identification and monitoring of the source
;        I would like you to participate on an incident investigation team to review this event. T of the investigation should include:
;i the gas; removal of the shims and replacement of the shield lid; and preparations for rel d
: s.      o Determination of the root cause(s) of this event using Taproot root cause tec$iiques.
loaded container to the spent fuel pool I would like you to participate on an incident investigation team to review this event. T of the investigation should include:
Determination of the root cause(s) of this event using Taproot root cause tec$iiques.
s.
o Identification of the source of the gas.
o Identification of the source of the gas.
o A review of welding procedures, processes, and work practices, includiag purging welding as is the normal practice for primary side welding activities, positioning of the person performing the welding and sampling for combustible gases.
o A review of welding procedures, processes, and work practices, includiag purging o
o An evaluation ofoperating experience at other utilities using the VSC-24 multi-asse
welding as is the normal practice for primary side welding activities, positioning of the person performing the welding and sampling for combustible gases.
                . scaled basket and with CarboZinc coating.
An evaluation ofoperating experience at other utilities using the VSC-24 multi-asse o
o A review ofprecursors to this event. The precursors may include, but not be limited to previous evaluations of the protective coating and experiences during the loading of the previous two containers.
. scaled basket and with CarboZinc coating.
9e?Mora y                           _
A review ofprecursors to this event. The precursors may include, but not be limited to o
N/Y
previous evaluations of the protective coating and experiences during the loading of the previous two containers.
N/Y 9e?Mora y


                      --                              -  .--      . - . _  --  ~- . . . -       - .. .
~-... -
I May 29,1996                                                                             .
I May 29,1996 Page 2 Mr. Castell is appointed chairman of this incident investigation team. It is anticipated that scope of this investigation will not need to be more broad then detailed above; however, shou the team believe that the scope needs to be changed, this should be discussed with me. I anticipate that this investigation can be completed by Friday, June 7,1996, The investigation should follow the instructions provided in procedure NP 5.3.3, " Post-Inc 1
Page 2
Critique and Investigation." Thus, your team will prepare a report ofyour investigati and will present your report to the Manager's Supervisory Staff. The report shoul Friday, June 14,1996.
!        Mr. Castell is appointed chairman of this incident investigation team. It is anticipated that scope of this investigation will not need to be more broad then detailed above; however, shou the team believe that the scope needs to be changed, this should be discussed with me. I anticipate that this investigation can be completed by Friday, June 7,1996, 1      The investigation should follow the instructions provided in procedure NP 5.3.3, " Post-Inc Critique and Investigation." Thus, your team will prepare a report ofyour investigati and will Friday, Junepresent 14,1996. your report to the Manager's Supervisory Staff. The report shoul G. J.     eld Plant Manager l
G. J.
                                                          ,e I
eld Plant Manager l
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9 Ff tan: OEce of Pubhc Mars Ts: 58Wid Pt Beach         Date:F29/96 Tirne:C:18:12                   Page 1 of 2 b-U.S. NUCLEAR REGULATORY COMMISSION Region III Office of Public Affairs 801 Warrenville Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT: RIII-96-21                                               May 29, 1996 CONTACT:           Jan Strasma 708/829-9663 Angela Dauginas 708/829-9662 E-mail: crpa30 nrc. gov NRC SENDS AUGHENTED INSPECTION TEAM TO REVIEW GASEOUS IGNITION INCIDENT IN SPENT FUEL CASK AT POINT BEACH NUCLEAR PLANT The Nuclear Regulatory Commission staff is sending an Augmented Inspection Team to the Point Beach Nuclear Power Station to review the unexpectect burning of a combustible gas during the welding of a lid on a spent fuel storage cask early Tuesday.
9 Ff tan: OEce of Pubhc Mars Ts: 58Wid Pt Beach Date:F29/96 Tirne:C:18:12 Page 1 of 2 b-U.S. NUCLEAR REGULATORY COMMISSION Region III Office of Public Affairs 801 Warrenville Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT:
RIII-96-21 May 29, 1996 CONTACT:
Jan Strasma 708/829-9663 Angela Dauginas 708/829-9662 E-mail:
crpa30 nrc. gov NRC SENDS AUGHENTED INSPECTION TEAM TO REVIEW GASEOUS IGNITION INCIDENT IN SPENT FUEL CASK AT POINT BEACH NUCLEAR PLANT The Nuclear Regulatory Commission staff is sending an Augmented Inspection Team to the Point Beach Nuclear Power Station to review the unexpectect burning of a combustible gas during the welding of a lid on a spent fuel storage cask early Tuesday.
The Point Beach plant, located near Two Rivers, Wisconsin, is operated by Wisconsin Electric Power Cornpany.
The Point Beach plant, located near Two Rivers, Wisconsin, is operated by Wisconsin Electric Power Cornpany.
The storage cask had been loaded with 24 spent fuel assemblies and moved from the spent fuel storage pool at the '
The storage cask had been loaded with 24 spent fuel assemblies and moved from the spent fuel storage pool at the plant to an adjacent work area.
plant to an adjacent work area.
As technicians began welding a-4,400 pound lid on the container, combustible gas inside the container ignited.
As technicians began welding a-4,400 pound lid on the container, combustible gas inside the container ignited.
Pressure from the burning gas moved the lid slightly, leaving it about one-inch out of place.                       The cask was filled with water at the time of the incident with a small air space at the top.
Pressure from the burning gas moved the lid slightly, leaving it about one-inch out of place.
The utility stopped the welding proceduro and is now investigating the cause of the gaseous ignition.                         Air monitors showed there was no roloaso of radioactivity from tho
The cask was filled with water at the time of the incident with a small air space at the top.
* container, and there is no evidence of damage to the spent fuel.       No one was injured in the incident.
The utility stopped the welding proceduro and is now investigating the cause of the gaseous ignition.
Air monitors showed there was no roloaso of radioactivity from tho container, and there is no evidence of damage to the spent fuel.
No one was injured in the incident.
Both reactors at the Point Beach plant were operating at the time and were not affected by the incident.
Both reactors at the Point Beach plant were operating at the time and were not affected by the incident.
Members of the NRC inspection team will join the NRC Senior Resident Inspector whc went to the plant early today Tuesday to monitor the utility's a.ctivities . The team members are from j             the NRC's Region III off:.co in Lisle, Illinois, and the NRC's l             Headquarters in Rockville, Maryland.
Members of the NRC inspection team will join the NRC Senior Resident Inspector whc went to the plant early today Tuesday to monitor the utility's a.ctivities.
The team members are from j
the NRC's Region III off:.co in Lisle, Illinois, and the NRC's l
Headquarters in Rockville, Maryland.
6/M
6/M


from: Ofrwe of Pubbc Apars To: $RMtlPt Beach     Dde:W29/96 Tane:08:19:16 e                                                                                             Page 2 ef 2 S
from: Ofrwe of Pubbc Apars To: $RMtlPt Beach Dde:W29/96 Tane:08:19:16 e
Page 2 ef 2 S
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The team will review the incident and monitor the utility's investigation.
The team will review the incident and monitor the utility's investigation.
'                        At the ceanpletion of its onsite review, the inspection team will present its findings to utility representatives in a meeting which is open to public observation.                   The schedule and location of the mooting will be announced later.
At the ceanpletion of its onsite review, the inspection team will present its findings to utility representatives in a meeting which is open to public observation.
The schedule and location of the mooting will be announced later.
A written report of the inspection findings will be issued several weeks after the conclusion of the inspection.
A written report of the inspection findings will be issued several weeks after the conclusion of the inspection.
This was the third spant fuel storage cask loaded at the Point Beach facility.               The other two were loaded without incident and placed on an outdoor storage pad.
This was the third spant fuel storage cask loaded at the Point Beach facility.
1                                                         #####-
The other two were loaded without incident and placed on an outdoor storage pad.
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              . . . . . . , .~ .. . .... .                 ....,...,n..
......,.~........
n ." '               m aw. m issuaui MY-29-96 WED 09:31 M EXTERM!. AFFAIRS                                         ~FAX        N0. 4142212884 rptr-29-1996 ges% FRdrt u!TI-Tu ruusua-                                   ~~--                                                 P. 01 4                       9 95/30/50         2383$         9000 353   1***           e
....,...,n..
                                                                                                                                                                    ~~m
n." '
                          ')                               .
m aw.
                                                                                      .                  N Noes           7gy,     io,
m issuaui MY-29-96 WED 09:31 M EXTERM!. AFFAIRS F
                                                                                            ?/& .. g                               _
~ AX N0. 4142212884 P. 01 rptr-29-1996 ges% FRdrt u!TI-Tu ruusua-
M @ 2. 7                            1 m                                      c.           -rA n
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                    ' cas                                                                 ~.                                                                 o CITIZENS' UI f..z,_m                                           .
4 9 95/30/50 2383$
                                                                                                                                                                          ~
9000 353 1***
ism.CumuN8t Smin300 - Musses.WT53103 ="(dor)251-3322                                                   .g           .
e
1-2m                                                    i EEFIDEISE RDCEE em IngTE BIIe at yOINT                                                 MC32RR P&&IIT                                         l 1BT MapIOhCE'ITE M WWomhSE EEF&esEDet Zst U.S.                                                                                 l l
~~m
WEDCU Gesus aseWW-emogue SEMR mangP suas TIaE' 2ar FZTE SENISBK                                                                         j A gas emplestem inside a higtr level naclear 1 smote silo at Wisconsist Electric Power DeM's (WESCO) Point femah Emaclear Flast has aw                   w'==== man's rarot =r         ~g                   ' anclear weste deep for the seceand time la five ansatans.
')
                                            " tham is the first medianotive weste stowere euspissiest at a U.S. meclear plass, seis Devia Meczist, wtwo Dimeetese of the citisees* Uttitty sense (CIB).                           att's time for IEEPCO to stop eag .a7-- = e== =ith moel er weste on san. =:-=< s==,                                     said w et.
N Noes
Assesding to the meelear hogalatexy camadssion M) imittel                                 ,
: 7gy, io, M @ 2. 7
at 2:45 a.m. on aqr 24th, an insiaantified gas . ignited asi        a its11 3-Leaded etek of *=e1L==se temste ===8 =<=seg 14 team of
?/&.. g 1
_   r- ; - '          ==*ing an emplosion. the esplosion eccurred gast s
c.
-rA n m
' cas
~.
o CITIZENS' UI f..z,_m ism.CumuN8t Smin300 - Musses.WT53103 ="(dor)251-3322
~
.g 2m 1-i EEFIDEISE RDCEE em IngTE BIIe at yOINT MC32RR P&&IIT 1BT MapIOhCE'ITE M WWomhSE EEF&esEDet Zst U.S.
WEDCU Gesus aseWW-emogue SEMR mangP suas TIaE' 2ar FZTE SENISBK j
A gas emplestem inside a higtr level naclear 1 smote silo at Wisconsist Electric Power DeM's (WESCO) Point femah Emaclear Flast has aw w'==== man's rarot =r ~g
' anclear weste deep for the seceand time la five ansatans.
" tham is the first medianotive weste stowere euspissiest at a U.S. meclear plass, seis Devia Meczist, wtwo Dimeetese of the citisees* Uttitty sense (CIB).
att's time for IEEPCO to stop eag.a7-- = e== =ith moel er weste on san. =:-=< s==,
said w et.
Assesding to the meelear hogalatexy camadssion M) imittel at 2:45 a.m. on aqr 24th, an insiaantified gas. ignited a its11 -Leaded etek of *=e1L==se temste===8 =<=seg 14 team of asi 3
_ r-
 
==*ing an emplosion. the esplosion eccurred gast s
pei*e to the welp the 9 i" *S *-goesk lid that tseiple ehest.
pei*e to the welp the 9 i" *S *-goesk lid that tseiple ehest.
4,                   .      The           d'ide 'tne                             Lited tape 2 ten lid, Leeving it tipped at                           a with         _
4, The d'ide 'tne Lited tape 2 ten lid, Leeving it tipped at a with 1 lack higher than mosam1. emere =enee no injuries.
1 lack higher than mosam1. emere =enee no injuries.                                                                                                               ;
WEFC0 has suspended fasther 1"<i of anclear - waste cayks
WEFC0 has suspended fasther 1"<i of anclear - waste cayks                                                                           )
)
,                                tantil it can dee-t== the cease of the m arf atant and whether may spent reel aves woes eessaged er taas ensplostem. Each 18 foot higts cask is imeded with 14 toes of medicestive waste, incloding 170 pommes of plutantum.                     Eena leessa maio contains the musiyaient                                                   -
tantil it can dee-t== the cease of the m arf atant and whether may spent reel aves woes eessaged er taas ensplostem. Each 18 foot higts cask is imeded with 14 toes of medicestive waste, incloding 170 pommes of plutantum.
sedioeotivikr of 340 Bir== nema-type emiplestems.                                           &oomaining to                                     '
Eena leessa maio contains the musiyaient sedioeotivikr of 340 Bir== nema-type emiplestems.
Fedasal guidelines, the weeto mest he )suyt safe far 10,000 years,.
&oomaining to Fedasal guidelines, the weeto mest he )suyt safe far 10,000 years,.
om o.oeme,es as, isss, amo. < a-arr cirsuit' co==s audse mark Frankel ekset down the panleau weste eng far the first time. Judge teamhmL ruled that the minblic servios Commission's (PSC)
om o.oeme,es as, isss, amo. < a-arr cirsuit' co==s audse mark Frankel ekset down the panleau weste eng far the first time. Judge teamhmL ruled that the minblic servios Commission's (PSC)
OS/Is/se at:ss                       TI/81 NO.0$$5                   P.cn1           g e..
OS/Is/se at:ss TI/81 NO.0$$5 P.cn1 g
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_    _    _.                      _ - . -        _ _ _                        .--          . -            - - - - - ._ _            - -      - - -= -
- - -= -
      . . . , ,          . . . . . . .        . . . . . . . . . . . . . . - . . . . . . . .          .........  ...... ..                            . . . i
i t*Y,28-BB WED 09:32 An EXTERNAL. AFfalRS FAX NO. 4142212884 P.02 Mtf=39-199G 1081G FAOM WIT 1.TV rt1LW4M'E 70 92212031 P.82
; ,      t*Y ,28-BB WED 09:32 An                     EXTERNAL. AFfalRS                               FAX NO. 4142212884                         P.02
. as/24/pe satae inswwe C** o**
  .                    Mtf=39-199G 1081G FAOM WIT 1.TV rt1LW4M'E                                           70               92212031         P.82
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earrissementel impact stateemus wee tetony named 2n====== is taLLed I
1 a
to consider how tems waste mer need to be stored in 1riscoasta und l
g
did not, pumpemely evelmuste enamonio enesgr alteamstives.
,                        earrissementel impact stateemus wee tetony named 2n====== is taLLed I
The PSC on May 20th Leeemd its use emeer roependay the daup.
!                        to consider how tems waste mer need to be stored in 1riscoasta und l                         did not, pumpemely evelmuste enamonio enesgr alteamstives.                                                 The PSC on May 20th Leeemd its use emeer roependay the daup.                                                     CUB will I
CUB will I
liasir AAle a zamouse chenmastes she acc's m.- esser, usyco has pieced two anclear weste loaded cashs em tae oncence storage paa                                                                     j
liasir AAle a zamouse chenmastes she acc's m.- esser, usyco has pieced two anclear weste loaded cashs em tae oncence storage paa j
                      ~                                                                                                                                       '
~
serior to tremeday's acciamet.
serior to tremeday's acciamet.
                                    "Werco said a moclear usate stesage _ . i *- cou24 mover                                                                   i happea," saia metritt.                                  It's amo mese season to keep ear sados
"Werco said a moclear usate stesage _. i *- cou24 mover
{
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Michigan sheseline from beoontag a deseoto yemmament neclear weste
happea," saia metritt.
!                        Gump," esmoloded marriet.
It's amo mese season to keep ear sados Michigan sheseline from beoontag a deseoto yemmament neclear weste Gump," esmoloded marriet.
i cut win be eekaar fee em immediate Fac 1 wM7 +'en and ma esses svvessaame unear zoom-L Mica to racpen the dump.
i cut win be eekaar fee em immediate Fac 1 wM7 +'en and ma esses svvessaame unear zoom-L Mica to racpen the dump.
.                                                                                          #M For amore infaamet. Lea, contacts 10mpid Hasseitt (808)-251-3322.
#M For amore infaamet. Lea, contacts 10mpid Hasseitt (808)-251-3322.
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95/89/96 31:38           T1/RX No.0645         P.001           g TOTR. P.02
95/89/96 31:38 T1/RX No.0645 P.001 g
TOTR. P.02


T .
T 4
4 NRC AIT ENTRANCE MEETING MAY 30.1996 Attendancs Wisconsin F,lectric Power Company R. E. Link                                 Vice President-Nuclear Power (by telecon)
NRC AIT ENTRANCE MEETING MAY 30.1996 Attendancs Wisconsin F,lectric Power Company R. E. Link Vice President-Nuclear Power (by telecon)
G. J. Maxfield                             Manager-PBNP G. M. Krieser                             Manager-Industry & Regu!atory Services S, A. Patuiski                             Manager-Nuclear Engineering A. J. Cayia                               Production Manager W. B. Fromm                               . Manager-Site Engineering D. D. Schoon                               Manager-Chemistry M. F. Baumann                             Manager-Nuclear Fuel Services J. A. Palmer                             Manager-Maintenance P. B. Tindall                           - Manager-Health Physics T. C. Guay                               Manager-Regulatory Services J. A. Holmes                             Training Coordinator E. J. Epstein                             Acting General Supervisor-Health Physics T. J. Jessessky                           Senior Project Engineer-Site QA
G. J. Maxfield Manager-PBNP G. M. Krieser Manager-Industry & Regu!atory Services S, A. Patuiski Manager-Nuclear Engineering A. J. Cayia Production Manager W. B. Fromm
    . T. G. Malanowski                         Senior Project Engineer-Licensing         l F. A. Flentje                             Regulatory Specialist
. Manager-Site Engineering D. D. Schoon Manager-Chemistry M. F. Baumann Manager-Nuclear Fuel Services J. A. Palmer Manager-Maintenance P. B. Tindall
- Manager-Health Physics T. C. Guay Manager-Regulatory Services J. A. Holmes Training Coordinator E. J. Epstein Acting General Supervisor-Health Physics T. J. Jessessky Senior Project Engineer-Site QA
. T. G. Malanowski Senior Project Engineer-Licensing F. A. Flentje Regulatory Specialist
{
{
Root Cause Evaluation Team C. A. Castell(Team Leader)                 Senior Engineer-Licensing -               i S. A. Pfaff                               Senior Engineer-Operating Experience S. J. Zepplin                             Training Specialist B. D. O'Connell                           Senior Engineer-Systems Engineering Sierra Nuclear Cornoretion T. McNulty                                                                           :
Root Cause Evaluation Team C. A. Castell(Team Leader)
l i
Senior Engineer-Licensing -
i S. A. Pfaff Senior Engineer-Operating Experience S. J. Zepplin Training Specialist B. D. O'Connell Senior Engineer-Systems Engineering Sierra Nuclear Cornoretion T. McNulty i
i i
i i


1 4
1 4
Nuclear Regulatory Commissian R. J. Caniano (Team Leader)   Chief, Plant Support Section #2, DRS, RIII T. J. Kobetz                 Senior Resident Inspector R. Laufer                     NRR Project Manager-KNPP R. Paul                       Reactor Inspector-RP, RIII J. Davis C. Withee
Nuclear Regulatory Commissian R. J. Caniano (Team Leader)
(                                   -
Chief, Plant Support Section #2, DRS, RIII T. J. Kobetz Senior Resident Inspector R. Laufer NRR Project Manager-KNPP R. Paul Reactor Inspector-RP, RIII J. Davis C. Withee
l l
(
l
l


.                                                                                                          l INTERNAL                                               .
INTERNAL
I
' CORRESPONDENCE I
                                              ' CORRESPONDENCE PBM 96-0329 To: W. J. Hennessy     A. J. Cayia         C. A. Castell         E. J. Enste:n M. F. Baumann From: G. J. Maxfield                                                                         i Date: May 30,1996                                                                           1
PBM 96-0329 To: W. J. Hennessy A. J. Cayia C. A. Castell E. J. Enste:n M. F. Baumann From: G. J. Maxfield i
Date: May 30,1996 1


==Subject:==
==Subject:==
NRC AUGMENTED INSPECTION TEAM (AIT) copy To:   W. B. Fromm         G. M. Krieser i
NRC AUGMENTED INSPECTION TEAM (AIT) copy To:
T. G. Staskal         G. J. Mrsfield           l P. B. Tindall . T. C. Guay         T. G. Malanowski R. E. :d                       i Al.4.1                                                                                 1 An entrance meeting was held today between NRC and NPBU representc:i .                               '
W. B. Fromm G. M. Krieser T. G. Staskal G. J. Mrsfield i
augmented inspection team (AIT) effort which commences today and is e, .;
P. B. Tindall.
T. C. Guay T. G. Malanowski R. E. :d i
Al.4.1 1
An entrance meeting was held today between NRC and NPBU representc:i.
augmented inspection team (AIT) effort which commences today and is e,.;
approximately one week.
approximately one week.
The NRC team members and areas of expenise are: '                                                   i i
The NRC team members and areas of expenise are: '
Roy Caniano (Team Leader and Chief, Plant Support Branch 2, Division e'           :P Safety, Region III).
i i
l Ron Paul (reports to Mr Caniano and will address radiation protenu consequences).                                                                               '
Roy Caniano (Team Leader and Chief, Plant Support Branch 2, Division e'
Tim Kobetz (PBNP Senior Resident Inspector)                                     ,
:P Safety, Region III).
Ron Paul (reports to Mr Caniano and will address radiation protenu consequences).
Tim Kobetz (PBNP Senior Resident Inspector)
Jim Davis (NRC headquaners, Ph.D. in metallurgy, will address materich it: 0 Rich Laufer (NRR Project Manager for Kewaunee Nuclear Power Plant)
Jim Davis (NRC headquaners, Ph.D. in metallurgy, will address materich it: 0 Rich Laufer (NRR Project Manager for Kewaunee Nuclear Power Plant)
Carl Withee (NRR, areas of expenise include shielding, criticality safety; w','
Carl Withee (NRR, areas of expenise include shielding, criticality safety; w','
Line 993: Line 1,279:
Paul Narbut (former resident inspector in Region V, NRR Vendor Brr nd.;
Paul Narbut (former resident inspector in Region V, NRR Vendor Brr nd.;
vendorissues)
vendorissues)
      %T9000 W.                                                                                       /2/jl
%T9000 W.
/2/jl


      . _ _  - . .          .    , . _ _ . - . _  _ . _        _ . . _ . _ _ - _ . _ _ . _ _ . _ _ _ _ . . _ . _ _ _    ...__..__..m
...__..__..m
                    .                                                                                                                    )
)
                                                                                                                                          \
\\
      ,        May 30,1996                                                                                                               1 l               Page 2                                                                                                                   )
May 30,1996 1
1 i
l Page 2 i
The eight areas which will be the focus of the AIT, the NRC team assignment, and the WE lead                             !
1 The eight areas which will be the focus of the AIT, the NRC team assignment, and the WE lead individuals are:
individuals are:
l.
l.
1.
1.
Line 1,007: Line 1,293:
(Kobetz/Cayia) 2.
(Kobetz/Cayia) 2.
Comparison of sequence of events to other cask loadings, identifying similarities and -
Comparison of sequence of events to other cask loadings, identifying similarities and -
differences. (Withee/W.Hennessy) i             3.
differences. (Withee/W.Hennessy) i 3.
Evaluation of actions during and following event (including EP event categories, other notifications, etc.) (Kobetz/Cayia) 4.
Evaluation of actions during and following event (including EP event categories, other notifications, etc.) (Kobetz/Cayia) 4.
Analysis of event (root cause evaluation) and corrective actions. (Davis /Castell) 5.
Analysis of event (root cause evaluation) and corrective actions. (Davis /Castell) 5.
Appropriate attention to system and component interfaces, including compatibility of cask with spent fuel.- (Narbut/ Wood)'
Appropriate attention to system and component interfaces, including compatibility of cask with spent fuel.- (Narbut/ Wood)'
(Duane Schoon will address chemistry-related areas)
(Duane Schoon will address chemistry-related areas) 6.
I 6.
Generic implications of event, including notifications made by vendor to other users of cask. (Davis and Narbut/Baumann)-
Generic implications of event, including notifications made by vendor to other users of cask. (Davis and Narbut/Baumann)-
7.
7.
Adequacy of overall radiation protection precautions. (Paul /E. Epstein) 1
Adequacy of overall radiation protection precautions. (Paul /E. Epstein) 1 8.
: 8.           Radiological consequences of this event. (Paul /E. Epstein)-
Radiological consequences of this event. (Paul /E. Epstein)-
G.J.M               eld i
G.J.M eld Plant Manager i
Plant Manager l
l l
l l                                                                                                                                         ,
l t
t l
l


05/30/96 AIT/PBNP CONTACT LIST NRC                               PBNP         Ext #
05/30/96 AIT/PBNP CONTACT LIST NRC PBNP Ext #
: 1. Kobetz                             Cayia         6668
1.
: 2. Withee                             Hennessy     6573
Kobetz Cayia 6668 2.
: 3. Kobetz                             Cayia         6668
Withee Hennessy 6573 3.
: 4. Davis                             Castell       6132 (through 06/01 TSC-A (06/03-End)
Kobetz Cayia 6668 4.
: 5. Narbut                             Wood         6317 Schoon (Chem) 6680
Davis Castell 6132 (through 06/01 TSC-A (06/03-End) 5.
: 6. Davis /Narbut                     Baumann       Page or 6221         '
Narbut Wood 6317 Schoon (Chem) 6680 6.
i.
Davis /Narbut Baumann Page or 6221 i.
: 7. Paul                               Epstein       6228
7.
: 8. Paul                               Epstein       6228 Other Contacts
Paul Epstein 6228 8.
* I
Paul Epstein 6228 Other Contacts 1.
: 1. Fritzie Flentje                                 6221
Fritzie Flentje 6221 2.
: 2. Terry Guay     (Reg Services Mgr)               6430                 1
Terry Guay (Reg Services Mgr) 6430 3.
: 3. Greg Maxfield (PBNP Manager)                     6212 f
Greg Maxfield (PBNP Manager) 6212 f


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UNITED STATES NUCLEAR REGULATORY COMISSION
UNITED STATES NUCLEAR REGULATORY COMISSION
                                                            . OFFICE-0F NUCLEAR REACTOR REGULATION r                                                                   WASHINGTON, D.C. 20555 l                                                                                                                   l l                                                                          May 31, 1996                             l l                                                                                                                   :
. OFFICE-0F NUCLEAR REACTOR REGULATION r
WASHINGTON, D.C.
20555 l
l May 31, 1996 l
l NRC INFORMATION NOTICE 96-XX: HYDROGEN GAS IGhiTION DURING VSC-24 MSB CLOSURE-WELDING l
l NRC INFORMATION NOTICE 96-XX: HYDROGEN GAS IGhiTION DURING VSC-24 MSB CLOSURE-WELDING l
Addressees All holders of operating licenses or construction permits for nuclear power
Addressees All holders of operating licenses or construction permits for nuclear power reactors.
;          reactors.
Independent spent _ fuel. storage installation designers and fabricators.
l Independent spent _ fuel. storage installation designers and fabricators.
l i
i       -Purpose l                                                                                                                   I The U.S. Nuclear Regulatory Commission (NRC) is issuing this information l-       notice to alert addressees to a hydrogen gas ignition event which occurred   -
-Purpose l
during the welding of the shield lid on a spent fuel storage cask at the Point Beach Nuclear Power Plant. It is expected that recipients will review the information for. applicability to their facilities and consider actions, as appropriate, to avoid similar problems. However, suggestions contained in this information notice are not NRC requirements; therefore,;no specific                                   '
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information l-notice to alert addressees to a hydrogen gas ignition event which occurred during the welding of the shield lid on a spent fuel storage cask at the Point Beach Nuclear Power Plant.
action or written response is required.                                   -
It is expected that recipients will review the information for. applicability to their facilities and consider actions, as appropriate, to avoid similar problems.
Description of Cirggastances                                                   .e u
However, suggestions contained in this information notice are not NRC requirements; therefore,;no specific action or written response is required.
l       On'May.28, 1996, a hydrogen gas ignition occurred during the welding of-the;                               j
Description of Cirggastances
      , shield lid on a VSC-24 MSB (multi-assembly sealed basket). The gas ignition displaced the shield-lid, leaving it in-place but tipped at a slight angle, l
.e u
with one edge about-= ir.d higher than normal.                                                               l
l On'May.28, 1996, a hydrogen gas ignition occurred during the welding of-the; j
                                                          ~3 tuema L       The VSC-24 MTC (multi-assembly transfer cask), a shielded lifting device                                   I utilized to transfer the MSB loaded with spent- fuel to the VCC (ventilated               -
, shield lid on a VSC-24 MSB (multi-assembly sealed basket).
concrete cask) for storage, had been placed-in the cask decontamination work area in'the auxiliary building. 'Approximately 30 gallons of spent fuel pool water had been drained to facilitato shield lid welding by creating an air space below the lid. The hydrogen gas ignition occurred during the-initiai. ion of-the shield lid welding, approximately 11 hours after the loaded MTC had
The gas ignition displaced the shield-lid, leaving it in-place but tipped at a slight angle, l
;        been removed from the spent fuel storage pool.
with one edge about-= ir.d higher than normal.
Discussion Following the event, gas and water samples collected from the MSB internals
~3 tuema L
!        showed detectable levels of hydrogen in the air space beneath the shield lid and dissolved in the MSC water. -The licensee then continuously purged the air space beneath the lid with nitrogen to prevent the accumulation of' combustible i
The VSC-24 MTC (multi-assembly transfer cask), a shielded lifting device I
gases, and moved the shield lid back into its original position. The MSB was
utilized to transfer the MSB loaded with spent-fuel to the VCC (ventilated concrete cask) for storage, had been placed-in the cask decontamination work area in'the auxiliary building. 'Approximately 30 gallons of spent fuel pool water had been drained to facilitato shield lid welding by creating an air space below the lid. The hydrogen gas ignition occurred during the-initiai. ion of-the shield lid welding, approximately 11 hours after the loaded MTC had been removed from the spent fuel storage pool.
:      then fully flooded.to eliminate the air space under the shield lid, and
Discussion Following the event, gas and water samples collected from the MSB internals showed detectable levels of hydrogen in the air space beneath the shield lid and dissolved in the MSC water. -The licensee then continuously purged the air space beneath the lid with nitrogen to prevent the accumulation of' combustible i
!      transferred back to the spent fuel storage pool. The licensee unloaded the spent fuel assemblies and placed them_in the spent fuel pool storage racks.
gases, and moved the shield lid back into its original position.
The MSB was then fully flooded.to eliminate the air space under the shield lid, and transferred back to the spent fuel storage pool. The licensee unloaded the spent fuel assemblies and placed them_in the spent fuel pool storage racks.
l
l


P
P
, u The'MTC/MSB was subsequently moved back to the decontamination work area for
, u The'MTC/MSB was subsequently moved back to the decontamination work area for j.
: j.                                     further inspection as part of the licensee's investigation of the combustible
further inspection as part of the licensee's investigation of the combustible gas burn.- A visual examination of the spent fuel assemblies, MSB and MTC
                                                ~
~
gas burn.- A visual examination of the spent fuel assemblies, MSB and MTC showed no evidence of damage as a result of the combustible gas ignition.
showed no evidence of damage as a result of the combustible gas ignition.
                                      'The investigation into the possible sources of hydrogen is. focusing on a zinc-based coating applied to the internal surfaces of the MSB. The zinc may have reacted chemically with the acidic water from the spent fuel storage pool to produce hydrogen. A minimum boron concentration is required to be maintained, j                                     as a criticality control, in the spent fuel storage pool water at Pressurized
'The investigation into the possible sources of hydrogen is. focusing on a zinc-based coating applied to the internal surfaces of the MSB. The zinc may have reacted chemically with the acidic water from the spent fuel storage pool to produce hydrogen. A minimum boron concentration is required to be maintained, j
;.                                    WaterReactors-(PWRs),
as a criticality control, in the spent fuel storage pool water at Pressurized WaterReactors-(PWRs),
i                                   An NRC Augmented Inspection Team (AIT) has been formed and is on-site to i
i An NRC Augmented Inspection Team (AIT) has been formed and is on-site to investigate the event.
investigate the event. The objectives of the AIT are to identify and
The objectives of the AIT are to identify and i
!                                    connunicate both the facts of the event and any generic safety concerns, and
connunicate both the facts of the event and any generic safety concerns, and to document'the findings and conclusions of the on-site inspection.
;                                    to document'the findings and conclusions of the on-site inspection.
i i
i                                                                                                                             ,
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i                                                                                                                               l l'
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4 e                                                                                                                               I i
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,                                                                  IN 9X-XX Month XX, 199X Page X of X Related Generic Co-inications (An optional list of other generic communications that have previously addressed the subject of the information notice.)
IN 9X-XX Month XX, 199X Page X of X Related Generic Co-inications (An optional list of other generic communications that have previously addressed the subject of the information notice.)
This information notice requires no specific action or written response. If you have any questions about the information in this notice, please contact (one of) the technical contact (s) listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
This information notice requires no specific action or written response.
If you have any questions about the information in this notice, please contact (one of) the technical contact (s) listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.
l I
l I
Brian K. Grimes, Director Division of Operating Reactor Support Office of Nuclear Reactor Regulation                 !
Brian K. Grimes, Director Division of Operating Reactor Support Office of Nuclear Reactor Regulation Technical contact (s):
Technical contact (s):


==Attachment:==
==Attachment:==
List of Recently Issued NRC Information Notices                               !
List of Recently Issued NRC Information Notices


      , jut 4-03-1996 11:30           SIEPRA iUCLEAR COPP                         408 438 52c5   P.02 tb     Oh       u   q 6/3/%       .
, jut 4-03-1996 11:30 SIEPRA iUCLEAR COPP 408 438 52c5 P.02 tb Oh u
SELECTION OF CARBO ZINC 11                                                 l l
q 6/3/%
l FOR USE IN COATING MSBs i
SELECTION OF CARBO ZINC 11 l
e  MSBs require coating to protect the spent fuel pool from corrosion products of the carbon steel shcIl and internals.
FOR USE IN COATING MSBs l
* An evaluation was completed in 1990 of available coating materials that could meet VSC operational requirements.
i MSBs require coating to protect the spent fuel pool from corrosion e
products of the carbon steel shcIl and internals.
An evaluation was completed in 1990 of available coating materials that could meet VSC operational requirements.
* Resistance to radiation.
* Resistance to radiation.
* Maintain intergity at relatively high 700'F temperature inside MSB.
Maintain intergity at relatively high 700'F temperature inside MSB.
e  Using all information sources available at the time including paint vendors, operators ofnuclear power plants, and relevent nuclear industry                   i experience, zine based inorganic coatings were selected.                                   )
Using all information sources available at the time including paint e
e  Carbo Zinc 11
vendors, operators ofnuclear power plants, and relevent nuclear industry i
                      =  Dimetcote 6
experience, zine based inorganic coatings were selected.
* Carbo Zinc 11 was selected because it was extensively used in the                         ,
)
nuclear industry and significant testing confirmed its performance.
Carbo Zinc 11 e
* Carbo Zinc 11 was the only coating approved for use in the Palisades spent fuel pool at the time of coating selection.
Dimetcote 6
* Main focus of selection involved performance in the spent fuel pool.
=
* Discussions with several nuclear organizations did not identify concerns                   ,
Carbo Zinc 11 was selected because it was extensively used in the nuclear industry and significant testing confirmed its performance.
with hydrogen generation due to contact with spent fuel pool water.
Carbo Zinc 11 was the only coating approved for use in the Palisades spent fuel pool at the time of coating selection.
* Hydrogen generation in a closed spent fuel cask filled with fuel pool water was never identified as a concern.
Main focus of selection involved performance in the spent fuel pool.
I
Discussions with several nuclear organizations did not identify concerns with hydrogen generation due to contact with spent fuel pool water.
_    l-l Ahf
Hydrogen generation in a closed spent fuel cask filled with fuel pool water was never identified as a concern.
I l-l Ahf


    ^
^
      ~ JL2K$3-1995~11:38         SIERRA IU1. EAR CORP                   408 438 5206 P.03 SELECTION OF CARBO ZINC 11 FOR USE IN COATING MSBs                                   ,
~ JL2K$3-1995~11:38 SIERRA IU1. EAR CORP 408 438 5206 P.03 SELECTION OF CARBO ZINC 11 FOR USE IN COATING MSBs (Continued)
(Continued) e Until incident at Point Beach, SNC was not aware of any combustible         !
Until incident at Point Beach, SNC was not aware of any combustible e
gas concerns with the VSC.                                                   !
gas concerns with the VSC.
e SNC has put together an action plan to address hydrogen generation within the MSB during loading operations.                                   !
SNC has put together an action plan to address hydrogen generation e
within the MSB during loading operations.
* Preliminary conclusion is that procedural changes will eliminate the potential for combustible concentrations of hydrogen being present during MSB closure operations.
* Preliminary conclusion is that procedural changes will eliminate the potential for combustible concentrations of hydrogen being present during MSB closure operations.
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w


JUi-ONiW6 11!38           SIEPPA FUCLEAR COPP                     408 438 5206 P.04 t
JUi-ONiW6 11!38 SIEPPA FUCLEAR COPP 408 438 5206 P.04 t
RELEVANT DIFFERENCES IN LOADING PROCEDURES PALISADES VS. POINT BEACH 5
RELEVANT DIFFERENCES IN LOADING PROCEDURES PALISADES VS. POINT BEACH 5
Point Beach Vent in shield lid closed prior to and during welding.
Point Beach Vent in shield lid closed prior to and during welding.
;                e  30 Gals. of water pumped out prior to welding shield lid.
30 Gals. of water pumped out prior to welding shield lid.
Amount of water pumped out determined by pumping time.
e Amount of water pumped out determined by pumping time.
MSB #3 sat for 24 hours after pumpdown prior to start of welding.
MSB #3 sat for 24 hours after pumpdown prior to start of welding.
Appearance ofloose Carbo Zinc on surface of spent fuel pool.
Appearance ofloose Carbo Zinc on surface of spent fuel pool.
Increases potential for hydrogen generation
Increases potential for hydrogen generation Shims for shield lid installed using pneumatic tool (tighter fit).
* Shims for shield lid installed using pneumatic tool (tighter fit).
Palisades 4
Palisades                                 .
Vent in shield lid open prior to and during welding.
l 4
                . Vent in shield lid open prior to and during welding.
* Slight negative pressure created in air space prior to and during welding.
* Slight negative pressure created in air space prior to and during welding.
e  75 gals. of water pumped out prior to welding shield lid.
75 gals. of water pumped out prior to welding shield lid.
Amount of water pumped out is measured.
e Amount of water pumped out is measured.
e  Lid welding activities started immediately after pumpdown.
Lid welding activities started immediately after pumpdown.
* No appearance ofloose Carbo Zinc on surface of spent fuel pool.
e No appearance ofloose Carbo Zinc on surface of spent fuel pool.
* Shims for shield lid installed by hand (looser fit).
Shims for shield lid installed by hand (looser fit).
                                        -      '3   -
'3


w es-issi '111.59
w es-issi '111.59 stERRd thiNUN CORP 408 38 5206 P.OS j
      ,                              stERRd thiNUN CORP                       408 38 5206   P.OS   j I
RECOMMENDED ACTIONS TO PREVENT RECURRENCE Follow approach used in 13 previously successful loadings at Palisades.
RECOMMENDED ACTIONS TO PREVENT RECURRENCE                                             !
* Follow approach used in 13 previously successful loadings at l
Palisades.
Assure loose Carbo Zine is removed from interior of MSB.
Assure loose Carbo Zine is removed from interior of MSB.
Pump out at least 75 gals. of water prior to welding shield lid.
Pump out at least 75 gals. of water prior to welding shield lid.
                          - Measure amount of water pumped out to assure accuracy.
- Measure amount of water pumped out to assure accuracy.
* Keep vent in shield lid open until water is completely removed.
Keep vent in shield lid open until water is completely removed.
* Maintain slight negative pressure in air space prior to and during welding.
Maintain slight negative pressure in air space prior to and during welding.
l
l Check for combustible gas in area of welding prior to start of
                    =  Check for combustible gas in area of welding prior to start of welding.                                                                     i
=
* Start shield lid welding activities immediately after pumpdown.
welding.
i Start shield lid welding activities immediately after pumpdown.
TOTAL P.05
TOTAL P.05


        . _      _  ..              .      .  .      _. . _      _ _ _      m     ._- ._ _ . . _ . . ___ _ _ _ - .
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From:
MarissaBailey(MGB))Nfdbb'.RASI From:
            - To:  MarissaBailey(MGB))Nfdbb'.RASI
. NCD2. CHI.' JAG, ARDl.ARPl TD:3 A 680% M
                          . NCD2. CHI.' JAG, ARDl.ARPl           TD:3 A 680%           M i
- To:
Date: Monday,= June.3, 1996 11:57 am
i Date: Monday,= June.3, 1996 11:57 am i


==Subject:==
==Subject:==
Draf t -CAL for the VSC-24 i
Draf t -CAL for the VSC-24 1
l
I Attached, in WP5.2 format, is-the draft CAL for the VSC-24 cask users.
-                                                                                                                        1 I
Comments from Hugh Thompson and 0GC have already beer incorporated.
Attached, in WP5.2 format, is-the draft CAL for the VSC-24 cask users.                                     j Comments from Hugh Thompson and 0GC have already beer incorporated.                                         '
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d
We did not add a sentence stating that NMSS will provide support to the Regions.
:.            We did not add a sentence stating that NMSS will provide support to the
If the Regions feel this is necessary, please suggest some wording.
;            Regions.                                                                                                   j
j We would like.to assure you that NMSS/SFP0 will support the Regions in resolving the issues in the CAL.
"'                      If the Regions feel this is necessary, please suggest some wording.                             '
- The Office of Public Affairs at HQ is planning to issue a press release upon issuance of the three CALs.
We would like.to assure you that NMSS/SFP0 will support the Regions in resolving the issues in the CAL.
Please contact Eric Leeds at (301) 415-8540 when~
            - The Office of Public Affairs at HQ is planning to issue a press release upon issuance of the three CALs.       Please contact Eric Leeds at (301) 415-8540 when~
' i 3
3
the CALs have been issued.
                                                                                                                        'i the CALs have been issued.
If you have any questions, please contact'me at (301) 415-8531 or Eric Leeds.
If you have any questions, please contact'me at (301) 415-8531 or Eric Leeds.
Thank you, l
Thank you, l
CC:           NCD2.ARI.KMK, NCD2.CHl.TJK1, NCD2.CHl.MEP, EJL, CJ                                           i s
CC:
I r
NCD2.ARI.KMK, NCD2.CHl.TJK1, NCD2.CHl.MEP, EJL, CJ i
s r
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_ . - .. .- .. - - . , - . . .              ~ . - - - - _ - . - - - - - - - - - - .                             -
~. - - - - _ -. - - - - - - - - - -.
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6/3 9:15 am i                   CAL No. X-XX-XXX Consumers Power. Company Wisconsin Electric. Power Company Entergy Operations', Inc.
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6/3 9:15 am i
CAL No. X-XX-XXX Consumers Power. Company Wisconsin Electric. Power Company Entergy Operations', Inc.


==SUBJECT:==
==SUBJECT:==
-    CONFIRMATORY ACTION-LETTER
CONFIRMATORY ACTION-LETTER


==Dear Sir (s):==
==Dear Sir (s):==
 
.j On June XX, 1996, representatives from NRC Headquarters, Regions III & IV and your company held a conference call to discuss your use of.the Pacific Sierra Nuclear Associate's Ventilated Storage Cask (VSC)-24 system. We initiated the conference call as a result of the May 28, 1996 event at the Point Beach Nuclear Plant involving a VSC-24 spent fuel storage cask. During the Point 1
                                                                                                                    .j On June XX, 1996, representatives from NRC Headquarters, Regions III & IV and                       !
Beach event, a hydrogen gas ignition occurred'during the. welding of the shield j
your company held a conference call to discuss your use of.the Pacific Sierra                       '
lid ~on a VSC-24 multi-assembly sealed basket.(MSB). The gas ignition displaced the shield lid, leaving it in place but tipped'at a slight. angle.
Nuclear Associate's Ventilated Storage Cask (VSC)-24 system. We initiated the conference call as a result of the May 28, 1996 event at the Point Beach Nuclear Plant involving a VSC-24 spent fuel storage cask. During the Point                         1 Beach event, a hydrogen gas ignition occurred'during the. welding of the shield                     j lid ~on a VSC-24 multi-assembly sealed basket.(MSB). The gas ignition                               !
j The VSC-24 multi-assembly. transfer cask (MTC), a shielded lifting device used to transfer the MSB loaded with spent fuel for storage, had been placed in the
displaced the shield lid, leaving it in place but tipped'at a slight. angle.                         j The VSC-24 multi-assembly. transfer cask (MTC), a shielded lifting device used                       I to transfer the MSB loaded with spent fuel for storage, had been placed in the
- cask. decontamination work area in the auxiliary building. Approximately 30 gallons of spent fuel pool water had been drained to facilitate welding of the shield lid by creating an air. space below the lid.. The' hydrogen gas' ignition occurred during the initiation of the shield' lid welding, approximately 11 hours after the loaded MTC had been removed from the' spent fuel storage pool.
                - cask. decontamination work area in the auxiliary building. Approximately 30 gallons of spent fuel pool water had been drained to facilitate welding of the shield lid by creating an air. space below the lid.. The' hydrogen gas' ignition occurred during the initiation of the shield' lid welding, approximately 11 hours after the loaded MTC had been removed from the' spent fuel storage pool.                       l Although the gas ignition caused no injuries.or radiological releases and no 8                       !
Although the gas ignition caused no injuries.or radiological releases and no 8
(             damage to the spent fuel or to the VSC components, the staff is concerned that                     .!
(
such an event has not been evaluated and could potentially result in more                             !
damage to the spent fuel or to the VSC components, the staff is concerned that such an event has not been evaluated and could potentially result in more severe consequences. Therefore, on May 29, 1996, an NRC Augmented Team Inspection (AIT) was formed and sent to the site to investigate the event.
severe consequences. Therefore, on May 29, 1996, an NRC Augmented Team                               '
The objectives of the AIT are to identify and communicate both the facts of the event and any generic safety concerns and to document the findings and conclusions of the onsite inspection.
Inspection (AIT) was formed and sent to the site to investigate the event.
Pursuant to a telephone conversation between (names and nositions of orincioal individuals reoresentina the licensee) and (names and nositions of *orincioal individuals reoresentina the NRC) on (date)
The objectives of the AIT are to identify and communicate both the facts of the event and any generic safety concerns and to document the findings and                           ;
, it is our understanding that you have'taken (or will take) the following actions prior to loading, or unloading, any spent fuel in a VSC-24 cask or placing a VSC-24 cask into the spent fuel pool:
conclusions of the onsite inspection.                                                                 '
(1)
Pursuant to a telephone conversation between (names and nositions of orincioal                       !
You will have assessed the potential for the generation and ignition of explosive gases during.all phases of operation of the VSC-24 system-i (2)'
individuals reoresentina the licensee) and (names and nositions of *orincioal individuals reoresentina the NRC) on                   (date) , it is our understanding that you have'taken (or will take) the following actions prior to loading, or unloading, any spent fuel in a VSC-24 cask or placing a VSC-24 cask into the spent fuel pool:
You.will have compensatory actions in place to minimize the potential
(1)     You will have assessed the potential for the generation and ignition of explosive gases during.all phases of operation of the VSC-24 system-                         i I
'i for the generation and ignition of explosive gases; (3)
(2)'   You.will have compensatory actions in place to minimize the potential                       'i for the generation and ignition of explosive gases;                                           '
You will have in place procedures to respond in the event of a gas ignition and the applicable personnel trained and briefed accordingly; and i
(3)     You will have in place procedures to respond in the event of a gas ignition and the applicable personnel trained and briefed accordingly; and i
~.
                                                                                                      --    -  ~.


M (4) 14 days prior to loading, or unloading, any spent fuel in a VSC-24 cask, D[
M (4) 14 days prior to loading, or unloading, any spent fuel in a VSC-24 cask, D[
the applicable plant personnel will contact the Director, Division of         y        i Reactor Projects, (applicable Region).                                              .
the applicable plant personnel will contact the Director, Division of Reactor Projects, (applicable Region).
Pursuant to Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, you are required to:
y Pursuant to Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, you are k'
k' l
required to:
: 1)     Notify me immediately if your understanding differs from that set forth above;
l 1)
: 2)     Notify me if for any reason you cannot complete the actions within the specified schedule and advise me in writing of your modified                 !
Notify me immediately if your understanding differs from that set forth above; 2)
schedule in advance of the change; and                                         4
Notify me if for any reason you cannot complete the actions within the specified schedule and advise me in writing of your modified schedule in advance of the change; and 4
: 3)   Notify me in writing when you have completed the actions addressed in this Confirmatory Action Letter.
3)
Issuance of this Confirmatory Action Letter does not preclude issuance of an order formalizing the above commitments or requiring other actions on the part of the licensee; nor does it preclude the NRC from taking enforcement action for violations of NRC requirements that may have prompted the issuance of this letter. In addition, failure to take the actions addressed in this Confirmatory Action Letter may result in enforcement action.                                     '
Notify me in writing when you have completed the actions addressed in this Confirmatory Action Letter.
Issuance of this Confirmatory Action Letter does not preclude issuance of an order formalizing the above commitments or requiring other actions on the part of the licensee; nor does it preclude the NRC from taking enforcement action for violations of NRC requirements that may have prompted the issuance of this letter.
In addition, failure to take the actions addressed in this Confirmatory Action Letter may result in enforcement action.
l The responses directed by this letter are not subject to the clearance procedures of the Office of Nanagement and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96-511.
l The responses directed by this letter are not subject to the clearance procedures of the Office of Nanagement and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No. 96-511.
I In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosure ((s), and your response will be placed in the NRC                     3 Public Document Room (PDR).       To the extent possible, your response should not               '
I In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosure ((s), and your response will be placed in the NRC 3
include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide                   '
Public Document Room (PDR).
the legal basis to support your request for withholding the information from the public.
To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Sincerely,
Sincerely, Regional Administrator (or designee)
* Regional Administrator (or designee)
(Director, NRR) (or designee)
(Director, NRR) (or designee)
(Director, HMSS) (or designee) l Docket No.
(Director, HMSS) (or designee) l Docket No.
License No.
License No.


nr./xf1T~ksu       ID:7085151096   JUN 04'96 o  .                                        9: 47No.bb2kO1 o
nr./xf1T~ksu ID:7085151096 JUN 04'96 9: 47No.bb2kO1 o
NOTE FOR ROY CANIANO:
o NOTE FOR ROY CANIANO:
Here's the draft announcement on the meeting-Any comments?
Here's the draft announcement on the meeting-Any comments?
l Jan                                                   ,
Jan e-mail: rjs2 g/a /Ja* #w phone: 708/829-9663 i
e-mail: rjs2 g/a /Ja* #w                             !
phone: 708/829-9663 i
I
I


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                                                        - DRAFT -
- DRAFT -
U.S.
U.S. NUCLEAR REGULATORY COMMISSION Region III Office of Public Affairs 801 Warrenv111e Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT:
NUCLEAR REGULATORY COMMISSION Region   III Office of Public Affairs 801 Warrenv111e Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT:         RIII-96-23 CONTACT:     Jan Strasma 708                                 June 4, 1996 i
RIII-96-23 CONTACT:
Angela Dauginas/829-9663 708/829-9662 E-mails opa30nrc.       gov 4
Jan Strasma 708 June 4, 1996 Angela Dauginas/829-9663 i
i NRC SPECIAL INSPECTION TEAM TO PRESENT FINDINGS OF i
708/829-9662 E-mails opa30nrc. gov 4
OF GAS BURN IN SPENT FUEL CASK AT POINT BEACH NUC will meet Friday _A Nuclear Regulatory Commission Augmented Inspection Team i                officials to discu(June 7) with Wisconsin Electric Power Company burn inPower Nuclear    a spent       fuel storage container May 28 at Station.                                          the Point Beachs Wisconsin.                     The Station is near Two Rivers, The meeting will be-at 10-a.p.m. in the Two Creeks Town i                Rivers, Wisconsin. Hall, located at State Highway 42 and Tapawingo Road north of T 4
i NRC SPECIAL INSPECTION TEAM TO PRESENT FINDINGS OF OF GAS BURN IN SPENT FUEL CASK AT POINT BEACH NUC i
l The six-person inspection team is headed b Branch Chief from the NRC's Region III Office. y Roy         Caniano, a Dr. Carl i              Paperiello, Director of the NRC's Office of Nuclear Naterial Safety the attend  andmeeting.
will meet Friday _A Nuclear Regulatory Commission Augmented Inspection Team officials to discu(June 7) with Wisconsin Electric Power Company i
Safeguards, and other NRc staff members will also i
burn in a spent fuel storage container May 28 at the Point Beachs Nuclear Power Station.
to weld a shield lid on the spent fuel storage container after was loaded with 24 fuel assemblies. There was no evidence of
Wisconsin.
;              damage result      to the of the  gasstorage burn. container er to the fuel assemblies as a j
The Station is near Two Rivers, The meeting will be-at 10-a.p.m. in the Two Creeks Town Rivers, Wisconsin. Hall, located at State Highway 42 and Tapawingo Road north of T i
;                    The spent the spent          fuel assemblies fuel storage    pool. were subsequently placed back in The investigation into the cause of the incident is focussing   on a zinc-based coating used on internal surfaces of the container.
i The six-person inspection team is headed b 4
acidic water hydrogen.          from the spent fuel storage pool to produceThe coating m The meeting between the NRC staff and Wisconsin Electric officials will be open to public observation. At the close of the meeting there will be an opportunity for questions and comments from members of the public.
l Branch Chief from the NRC's Region III Office. y Roy Caniano, a Paperiello, Director of the NRC's Office of Nuclear Naterial Dr. Carl i
                                                    #9i#i
Safety and Safeguards, and other NRc staff members will also attend the meeting.
                                    .-            .                                -.      - .    . _ .}}
to weld a shield lid on the spent fuel storage container after i
was loaded with 24 fuel assemblies.
There was no evidence of damage to the storage container er to the fuel assemblies as a result of the gas burn.
j The spent fuel assemblies were subsequently placed back in the spent fuel storage pool.
The investigation into the cause of the incident is focussing on a zinc-based coating used on internal surfaces of the container.
acidic water from the spent fuel storage pool to produceThe coating m hydrogen.
The meeting between the NRC staff and Wisconsin Electric officials will be open to public observation.
At the close of the meeting there will be an opportunity for questions and comments from members of the public.
#9i#i
. _.}}

Latest revision as of 11:11, 12 December 2024

FOIA Request for Document Re Event at Point Beach Nuclear Power Plant,Involving Gaseous Ignition Incident During Welding of Spent Fuel Cask on 960528
ML20129G619
Person / Time
Site: Point Beach  
Issue date: 08/05/1996
From: Dums D
CITIZENS' UTILITY BOARD
To: Racquel Powell
NRC OFFICE OF ADMINISTRATION (ADM)
Shared Package
ML20129G560 List:
References
FOIA-96-322 NUDOCS 9610030105
Download: ML20129G619 (47)
v • d • e


Text

-

CITIZENS' UTILITY BOARD l

16 N. Carroll St., Suite 300 Madison, WI 53703 + (608) 251-3322 + FAX (608) 251-7609 -

EREIDOM 0F INFORMATION i

ACT REQUEST August 5, 1996 Porn-16

.32t Mr. Russell Powell Branch Chief FOIA/LPDR Nec/d 9 /M7d Nuclear Regulatory Commission Washington, D.C.

20555 Re:

Freedom of Information Act Request

Dear Mr. Powell:

Pursuant to the Freedom of Information Act, 5 U.S.C.

522, as amended and 10 C.F.R. Part 9.41, the Wisconsin Citizens' Utility Board (CUB) requests the following documents:

1.

Please provide any and all documents that make a specific reference to the event at the Point Beach nuclear power plant, Dockets 50-266 and 50-301, involving a gaseous ignition incident during the welding of a spent fuel cask.

This event was identified by the NRC in Preliminary Notification of Event or Unusual Occurrence PNO-III-96-033 on May 28, 1996; i

2.

Please provide any and all documents that address the generation of explosive gases during any phase of operation of the VSC-24 system; 3.

Please provide any and all documents that address the ignition of explosive gases during any phase of operation of the VSC-24 system.

  • On June 4, 1996 CUB submitted a FOIA request to the NRC requesting documents responsive to items 1-3.

The NRC completed its response to CUB's June 4, 1996 FOIA, identified by the NRC as FOIA-96-244/ June 10, 1996, on July 25, 1996.

CUB is re-submitting its FOIA request for items 1-3 to obtain documents in the agencies possession for the period of time following the date the NRC received CUB's June 4, 1996 FOIA to the date the NRC receives this FOIA request.

9610030105 960923 PDR FOIA DUMS96-322 PDR

,c_A1 g

., war,

4.

Please provide any and all documents that address increased neutron multiplication in the fuel in a cask because of boron precipitation from a chemical reaction among the borated water and cask materials.

5.

Please provide any and all documents that address the effect of.a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool on fuel cladding integrity.

6.

Please provide any and all documents that address the effect

)

of a precipitate-formed by a chemical reaction of zine with i

acidic borated water from a spent fuel pool on the heat i

transfer characteristics of a VSC dry storage cask.

7.

Please provide any and all documents that address the behavior of a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool under long-term exposure to neutron and gamma radiation.

8.

. Please provide any and all documents that address the behavior of a precipitate formed by a chemical reaction of zine with acidic borated water from a spent fuel pool under high temperatures.

9.

Please provide any and all documents that address the effect of a zinc reaction with the acidic borated wator from a spent fuel pool on the characteristics of MSB anti-corrosion coatings.

10.

Please provide any and all documents that address the effect i

of a zinc reaction with the acidic borated water from a spent fuel pool on the retrievability of sp6nt fuel.

11.

Please provide any and all documents that address the effect of a zinc reaction with the acidic borated water from a spent fuel pool on the reactor coolant system.

For purposes of this request, please consider " documents" to include reports, studies, test results, correspondence, memoranda, meeting notes, meeting minutes, working papers, graphs, charts, diagrams, notes and summaries _ of conversations and interviews, computer records, and any other form of written communications including internal NRC memoranda.

Pursuant to and in compliance with 10 C.F.R. 9.41 of the agency's regulations and 5 U.S.C. 552 governing requests for waiver of fees, CUB puts forth the following information.

CUB was incorporated pursuant to Chapter 181, 1979, of the 1 l

l

O Wisconsin Statutes.

CUB is exempt from Federal income tax under Section 501(c)(4) of the Internal Revenue Code.

CUB is also exempt from Wisconsin franchise tax.

The restricted fund (public interest fund) is exempt from Federal income tax under Section 501(c)(3) of the Internal Revenue Code.

The fund is also exempt from Wisconsin income taxes.

The restricted fund (public interest fund) was established on February 1, 1981, and reorganized on April 28, 1986 to cocrespond to the new structure of the CUB.

The fund engages in charitable, scientific, literary and educational activities on behalf of CUB.

CUB has 20,000 members who are residential ratepayers in Wisconsin.

CUB represents the more than two million residential ratepayers in the state.

CUB's purpose continues to be the statutory purpose set forth under sec. 199.02, Wis. Stats.:

...to promote the health, welfare and prosperity of all the citizens of this state by ensuring effective and democratic representation of individual farmers and other individual residential utility consumers before regulatory agencies, the legislature and other public bodies and by providing for consumer education on utility service costs and on benefits and methods of energy conservation.

CUB seeks the requested information to become informed of the causes, consequences, and remedies of and for an incident which took place on May 28, 1996 involving the use of the VSC-24 storage system for spent nuclear fuel.

CUB intends to use the information to assist in its participation in any proceedings before the NRC, before state regulatory agencies, and as part of CUB's ongoing ef fort to educate the public on nuclear waste storage issues in Wisconsin.

The information sought, is not, to the best of our knowledge, in the public domain.

The general public in Wisconsin has displayed great interest in nuclear waste issues and have a direct interest in NRC actions regarding the VSC-24 dry cask storage system.

CUB has demonstrated its ability and commitment to inform the public on all important nuclear waste storage issues in Wisconsin.

CUB provides this information free of charge through newsletters, educational pamphlets, and correspondence to its members, other residential ratepayers, legislators, and policy makers, and has neither a commercial nor a private interest in the agency records sought.

Under the amended fee waiver standard, CUB is clearly entitled to a full waiver of all search, review and duplication fees.

This standard calls for such a waiver, "if disclosure of the information is in the public interest because it is likely to contribute significantly to the public understanding of the operation or

]

activities of the government and is not primarily in the commercial interest of the requester." 5 U.S.C. 552 (1)(4)(A)(111).

In light of the foregoing, CUB meets this standard on its i

face.

CUB has no commercial interest in this matter, but rather seeks this information to help the general public better understand the role of government in regulating the nuclear industry's radioactive waste storage activities.

For the reasons cited above, CUB's request falls squarely within the Congressional intent in enacting the Freedom of Information Act and the fee waiver provision. CUB, therefore, asks that the NRC grant a full fee waiver for this FOIA request.

Thank you for your anticipated cooperation.

If you have any questions in regards to this request, please feel free to contact me at your earliest convenience.

Please contact me before acquiring and sending the requested information if the fee waiver is not applied.

Sincerely, b

e Dennis Dums i

Research Director 4

4 i

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4 nummmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmes Copyrighted Document l

Addressed Under FOIA i

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l For hard copy, refer to PDR Folder:FOIA N-su mummmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm, l

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FOIA Name & Number:

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l Pages: Sco/td 8-3 7 boaEh 7-a 3 -9 4 /tzs?m j

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QUESTIONS FOR WISCONSIN ELECTRIC POWER COMPANY Related to VSC-24 Cask Loading Incident A.

Backcround Information, 1.

Please provide a detailed description of the circumstances leading up to the event. If possible, please describe details on how the lid lifted, other sources of combustible materials present at the time, and other evolutions in progress in the vicinity of the cask decontari.' nation area.

Had there been any problems or abnormalities during fuel movement or transfer?

Any personnel contaminations?

2.

What were the characteristics of the spent fuel placed in the affected MSB? Were there any significant fuel characteristic differences compared to previous cask loadings?

(Initial enrichments, burnups, heat generation rates, etc.)

3.

What was the condition of the fuel assemblies placed in the MSB? Were there previously known leakers? What inspections were performed to verify the condition of the fuel before loading into the MSB?

4.

When and how much water was drained from the MSB prior to beginning welding preparations? How was the water drained out of the MSB?

5.

Were the drain and fill ver.ts opened or closed at the time of the event?

6.

Was any cover gas used to backfill the space voided by water draw-down? If so, what type?

7.

What is the typical time between removing the cask from the pool to wold commencement? Is the 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> typical?

11 Qtrrent Conditions / Status 1.

What is being done to maintain " safe conditions?"

2.

What actions are being taken to determine the type of explosive gas that ignited?

What is the current generation rate?

3.

What sort of gas sampling was done before, during and after the event?

4.

What were the assumptions used to determine the 55 hour6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br /> time limit for drain down....what is assumed to occupy the annulus between the MSB and the transfer cask?

t t

5.

What weld method was used? Type of shield gas?

6.

What inspections / actions are planned for examining the fuel and MSB? Is there an estimate of pressure induced damage to the MSB following the event? Are there plans for sampling or monitoring the water in the MSB? What actions will be taken after the sample analyses are obtained?

C Potential Generic Issues 1.

ilas Point Beach notified others? Press release?

2.

Plans for notifying other vendors and licensees?

4 0

i CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS ELAPSED TIME (HRS: MINS)

EVENT LOAD #1 LOAD #2 LOAD #3 Serial #

(MSB-01)

(MSB-03)

(MSB-02)

Start MSB fill 0

0 0

MSB into SFP 1:19 4:15 1:15.

1Aad fuel 15:19 12 hr 19.30 12.5 hr

~ 13.57 10.7 hr Shield lid in place 19:04 22:45 17:05 MSB breaks SFP surface 23:09 26:35 18:25 30 gal. Pump down 23:19 26:41 18:35 MSB out of SFP 23:49 27:00 19:00 Tack welds begin 36:34 37:10

~29:00 Shield weld complete '

42:19 42:30

.{

Weld structural lid 54:19 6.5 hr 65:00 12 hr Stnictural lid seal weld 56:04 68:00 Drain MSB -

61:19 70:00

  • - Not performe<!

MSB - Multi-Assembly Sealed Basket SFP - Spent Fuel Pool 1

i

i e CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS TIME AND DATE OF EVENT EVENT LOAD #1 LOAD #2 i

LOAD #3 9

i 4

Serial #

(MSB-01)

(MSB-03)

(MSB-02) j-Start MSB fill 0911 : 12/11/95 1800e : 5/20/96.

2145 : 5/26/96 l

MSB into SFP

.1030 2215 2300e Load fuel 1235-0030 : 12/12 0100-1330 : 5/21 0100e-1142 : 5/27 4

Shield lid in place 0415 1645 1450 MSB breaks SFP surface 0820 2035 1610 30 gal. Pump down 0830e 2041 1620e MSB out of SFP 0900 2100 1645 Tack welds begin 2145 0700e : 5/22 0245 : 5/28 Shield weld complete 0330 : 12/13 1230 Weld structural lid 0900-1530 2300-1100e :

(

5/23 Structural lid seal weld 1640-1715 1400e Drain MSB 2145-2230 1600e-1641 e - Time of event not recorded; estimate based on adjacent recorded events, i

  • - Not performed MSB - Multi-Assembly Sealed Basket SFP - Spent Fuel Pool

1 r

j i

CHRONOLOGY OF RELEVANT DRY CASK OPERATIONS

]

ELAPSED TIME (HRS: MINS)

EVENT LOAD #1 LOAD #2 -

LOAD #3 Serial #

(MSB-01)

(MSB-03)

(MSB-02)

Start MSB fill 0

0 0

MSB into SFP 1:19 4:15 1:15 Load fuel 15:19 12 hr 19:30 12.5 hr 13:57 10.7 hr Shield lid in place 19:04 22:45 17:05 MSB breaks SFP surface 23:09 26:35 18:25 30 gal. Pump down 23:19 26:41 18:35 MSB out of SFP 23:49 27:00 19:00 Tack welds begin 36:34 37:00 29:00 Shield weld complete 42:19 42:30 Weld structural lid 54:19 6.5 hr 65:00 12 hr Structural lid seal weld 56:04 106:00' Drain MSB 61:19 70:00

  • - Not performed 4

MSB - Multi-Assembly Scaled Basket l

SFP - Spent Fuel Pool 1 - Drained down prior to completing structural lid seal weld 19/%

.h i

TIME AND DATE OF EVENT EVENT LOAD #1 LOAD #2 LOAD #3 Serial #

(MSB-01)

(MSB-03)

(MSB-02)

Start MSB fill 0911 : 12/11/95 1800e : 5/20/96 2145 : 5/26/96 MSB into SFP 1030 2215 2300e Load fuel 1235-0030 : 12/12 0100-1330 : 5/21 0100e-1142 : 5/27 Shield lid in place 0415 1645 1450 MSB breaks SFP surface 0820 2035 1610 30 gal. hmp down 0830e 2041 1620e MSB out of SFP 0900 2100 1645 Tack welds begin 2145 0700e : 5/22 0245 : 5/28 Shield weld complete 0330 : 12/13 1230 Weld structural lid 0900-1530 2300-1100e :

5/23 Structural lid seal weld 1640-1715 0405e' 5/25 Drain MSB 2145-2230 1600e-1641 :

5/23 e - Time of event not recorded; estimate based on adjacent recorded events.

  • - Not performed MSB - Multi-Assembly Sealed Basket 1 - Drained down prior to completing structural lid seal weld SFP - Spent Fuel Pool

4

, a ISSUE STATUS AND EXIT NOTES Item 5 Determine if approoriate attention was given to the condition of systems and components associated with dry cn* evolutions. including comnatability of the dry end with soent fuel oool conditions.

I examined the licensee's overview and control of the multi-assembly stoage basket (MSB) during fabrication and upon receipt. I was verified that licensee were very involved in the oversight of fabrication by the contracted fabricators at the various fabrication sites. The licensee had essentially full time representation at the fabrication sites and documented their presence through the use of HOLD POINTS in the contruction documents. I observed that licensee representatives independently verified important parameters such as cleanliness, weld size, and material certifications. Their verifications included detailed parameters such as paint thickness. I verified that on site receipt inspection also independently verified that the casks received on site had been maintained in aquality condition. I reviewed the procedures records for using the MSB and verified quality conditions had been maintained.

I concluded that the licensee had given appropriate attention to the condition of equipment-associated with the dry cask storage evolutions.

The occurrence of the event makes it clear that appropriate attention was not given to the chemical compatibility of the MSB zine paint and the SFP boric acid conditions. Neither the j

i designer nor the licensee forsaw the potential for the chemical reaction that occurred. Several suggestions, that might have alerted the involved parties, were available. First, the paint manufacturer's specification sheet stated that the paint was not reccommended for immersion in acids. Secondly, the licensee studied the incompatibility of the paint and SFP boric acid in a study they conducted in July 1995. The study noted the potential for a zine borate pricipitate and possible coating on SFP fuel. Hydrogen generation was not addressed.. The study was a proactive effort and showed a good reflective atttude. Unfortunately, the study only focused on potential reactor plant effects and not on the potential effects on dry cask storage. I concluded that the problem occurred due to inadequate design review for chemical compatibility.

Ite m 6 Determine any notential generic implications of the event. Evalunie the technical supoort by the vendor for the prevention of similar events.

Preliminarily we determined the following potential generic issues as lessons learned from this event:

1. The adequacy.of the chemical compatibility studies conducted during design reviews for all cask designs and facility environments should be reviewed. For cases

- where a detailed review was not conducted appropriate action should be taken.

j

. f l

e i

2.

The potential for the presence of chemical reaction residues on fuel and storage cask components currently in day storage should be assessed. Additionally, the acceptability of any effects of the residue should be assessed for the remainder of the interim storage period.

3.

J i

i 4

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POINT BEACH QUESTIONS For John Jankovich:

OUR AIT CHARTER ITEMS 5 &6 ARE: (5)TO DETERMINE IF APPROPRIATE ATTENTION WAS GIVEN TO THE CONDITION OF COMPONENTS AND THEIR COMPATIBILITY WITH SPENT FUEL POOL CONDITIONS AND (6) DETERMINE ANY GENERIC ISSUES, AND EVALUATE THE TECHNICAL SUPPORT BY SNC FOR THE PREVENTION OF SIMILAR EVENTS The SNC inspection team should focus on items 5 and 6 and the following specific questions.

f j

1. Did the SNC design review include a corrosion engineer. Should the designers have anticipated the Hydrogen generation in the SFP?
2. What was the design basis for the paint selection? Reference the COC pg A-2 " potential for fire and explosion should be addressed." and SER Sect 2.6. What environmental

- i compatibility study was done? How did they address the paint specification proldbition against the use of Zine with acid?

3. What is SNC's investigative plan for this event'?
4. Was their Part 21 evaluation performed? Were we and the customers notified?
5. Was SNC aware of the licensee's concern with the effect of Zinc accumulation in the i

SFP (from the MSB) in July 1995. What was their assessment and action?

6.

n, Why was the paint not considered important to safety?

I 7.

Was SNC aware of MSB lid welding problems (moisture and blowouts) enchntered at 4

g Palisades? What was their action?

h 8.

Reportedly the paint was qualified at Oak Ridge. What were the paint qualification

..V requirements?

9. The SAR Pgs 1-8,1-9 state the purpose of the paint was to " protect fuel pool I

chemistry." What was meant by this statement.

10. Is SNC involved with the VSC-24 user's group?

NOTE for John: Wisconsin Electric is authorized by SNC to fabricate their own VSC-24's.

They did so using PCC, US Tool and Die, Regal Industrial Inc (for painting), and (in the future) March Metalfab d/f

O g,

For Charlie liaughney 1.

Please arrange to have the team briefed on the VSC-17 problems with hydrogen addressed by Fawn Shillingslaw..We need to have a cohesive story on why those problems did or did not relate to the VSC-24 problem.

2.

What did the NRC design review include? Was the chemical compatibility of paint /SFP water included? Does the SRP have an item on this? We expect this question after the exit. Will someone fandliar with the review process be at the exit ?

3.

Please have a chemist review the chemical reaction that occurred. Are there ways to mitigate / prevent the reaction with PH control, etc.

e

Status ofIncident Investigation Hydrogen Burn During Loading of Third VSC-24 Investigation Scope and Status:

- Root Cause Evaluation Main effort thus far has been data gathering and interviews. Preliminary events and causal factors chart completed (6/5). Investigation team consensus is that the root cause lies in design issues category. This is based on preliminary review of the investigation into why CZ-i l was being used as a coating for the VSC-24 internals. Additional analyn of all causal factors is in progress.

- Source of Gas Substantial evidence has been gathered that shows the source of gas to be hydrogen produced by Zinc-Acid reaction. No substantial evidence has been found that would gove any of the following theories directly contributed to the production of hydrogen:

Faulty Carbo Zine iI paint Contamination of CZ 11 paint Improper Application of CZ lI paint Radiolysis production of112 gas inadvertent introduction Combustible gas during loading process Welding issues Review of welding issues has not revealed any direct contributor to this event.

- Experience at Utilities Palisades is considered the most relevant experience to compare. Two Consumers Power dry storage e.sperts arrived on 6/5/96. Further analysis of differences and similarities is needed and is proceeding.

Review of Precursors Four Precursors have been identified:

Small burn during grinding in 2nd cask loading.

Indication of pressure build up on 2nd cask after installation of shield lid.

Chemical evaluation of compatibility of coatings.

Visual Evidence of gas production.

An additional possible precursor is: Film' residue seen during initial filling of MSBs i

/M

Incident Investigation Process 1.

Investigation Planning identify personn-l involve e

Develop a preliminary E&CF chart Identify objective (s) of the Incident Investigation team identify areas requiring investigation e

2.

Information Collection Collection of physical evidence a

Interviewing of personnel Collection of records, logs, drawings, etc e

3.

Determine Sequence of Events Develop a detailed E&CF chan e

4.

Identify events causal factors / conditions Barrier Analysis Change Analysis 5.

Identify Root Cause(s) includes identification of any " generic" causes e

6.

Develop correctise actions 7.

Report development

POINT BEACH VSC-24 STORAGE CASK EVENT - MAY 28, 1996 DISCUSSION e

' Event Followuo AIT Findings & Conclusions Vendor Inspection Findings Sumary of Public Concerns hitial Reaulatory Acticas 6

Issued IN 96-34 on May 31, 1996, CALs Issued June 3. 1996 to Affected Licensees (Pt. Beach. Palisades ANO).

Future Reaulatory Actions e

Generic Comunications:-

Cask Vendors Utilities operating or planning ISFSIs Modify SRP for-Storage Casks b

x%

L

A Good rning and welcome to this exit meeting following the completion of the NRC Mit I am Roy Caniano, Chief of the Plant Support Branch in Region III. Over tYe past ten days I also served aj% t0 7ipM s the eam leader for this inspection effort.

H l

4 tris is tne fui v i u n iur we wrr and = standard policy fcr the';c type:; of p

' meetinal inspe on, his open for puou servation. For, he pur ose of this spe t

discussi our inspec ings will be b n the NRC and

,j p, y Point Fol ing the s ~ ns we wil en ed to opc floor for y ques any observe ma ave. To ass his effort, Jack r.obe, D uty Divis,on D1 tor fr Region III will facilita that portion of the meeting.

At this time I would like to go through a round of introductions of both NRC and Point Beach staff. (INTROS...)

Thank You. Before we get started with further discussions, and for the benefit of attendees that may not be familiar'with dry cask operations and the event that occurred here on May 28, Tim Kobetz, the Senior NRC Resident Inspector here will give a brief overview of the cask system utilized here at Point Beach and will briefly summarize the event. As findicated earlier, I would appreciate that any questions arising from the summ4ry be held until later.

((

(TIM'S OVERVIEW) f

- / Thank you Tim.

I Last Thursday was the formal initi ion of the fkt/and the entrance meeting with I

Point Beach management. At that me we summarized the principle reason for the I

')W which was attaining an un rstanding of the root cause of the hydrogen generation causing the -hydrogen burrr during the welding operation on May 28th.

In addition at the entrance meeting we also discussed several other objectives V) t g

These included :

, M J In addition to the NRC staff here at Point Beach we also had several NRC staff m24 members at the Sierra Nuclear facility in California. Sierra Pcle:Hs4he AMY -designeMor--the-cask-system-used-here-at Point-Beach. C,/2 We believe that over the past week and a half that we have gained a good understanding of the root cause of the event as well as an understanding of the circumstances leading up to the event. In addition,we were also able to assess, by direct observations, your initial response activities immediately following the event. As you are aware, Tim Kobetz followed the event immediately after its occurrence with additional NRC staff being dispatched from Region III, soon after we became aware of the event. Until the cask was safely moved back into the spent fuel pool NRC provided round the clock oversight.

I would now like to provide a general overview of our assessment of the event as well as the circumstances leading up to the event and your response to it.

I will then turn the discussions over to each of the/4Wteam members introduced earlier who will provide a more detailed summarization of our findin s.

770 W Our initial evaluation of the event confirmed that the/e were no releases of radioactive materials from the cask following the b e ouen h en and no increase y

in radiation levels surrounding the cask. As I

employees the environment or members of the public.such there was no \\ptEF 7

N1

h O

Although some #Gihvweaknesses we identified during re ery operations which will be discussed later, overall, your raspense and af-f returning the cask

~

to the spent fuel pool,4 W W -

a~v d Ifg/IWithregardtotheeventitselfandasTimipdcatedearlier,thec se of the

.bes(on the welding of the third c sk was Me rxM af hydrogen present p

()

at the location of one of the wel

. The hydrogen was pr nt as a result of the chemical reaction when the ntfuelpoolwaterwasaddedtothecaskf during loading operations. Basef pon our review of the pr ious two cask loads of t!.e sec^ " M tt.:x:: ^" ' - s Thk D=+cgen generait meing:Imrdimy

' t

' U l 4

r, we also determined that thereillas ev3Me+ h

.J of#^ ~^ " -"' "ith- = ve =:ac;;...m n u,; C '

=lhe inp M-W-

% h necurred I

witd 43 ---99

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ev.idencA th:t. g 9 ;;; 3 r J ) '

ev tku t wiUi me ivauing or 4 E

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Although these problems were n ed by severa a'-

~ 'ayees involved in the loading of the aneombcask.rthere was limited followup to the occurrences in i,

an attempt to identify the causes.

Had a detailed technical review been accomplished you may have identified hydrogen was present and as such, it is quite possible that the event with the third cask could have been prevented.

n At this time I would like each of the individual

. staff members to summarize their inspection findings and identify any issues that will warrant additional followup. Following each summary I would request that you respond to our assessment.

~

~~

Closing:

you for 1me today. The, re ort 1inmarizing our fi Trg's wi3J -

be within t xt three weeks.

s indicated,there w ever ems ill warrantin followup.

Thesa be identifieo in the nspect report.

this time the exit M is concluded. I uld now like to en the meeting for estions form members o e public or medi.

s previously 1 cated Jack i/p Grobe wi facilitating that e and at this tfiil would like to rn the d

meeting over to a(

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I Number 1.

The adequacy of the chemical compatibility studies conducted during design reviews for all cask dcrigns and facility environments should be reviewed. For cases where a detailed review was not conducted, appropriate action should be taken.

$ Examples versights i ntified from thi event inc the po ' bili]ty of the tion

'h ogen from inc paint -

borated water

etion, j

i water ~

sion in id's shieldi material (in desig

[ Thia l

includes dy of the etting of Q7 which occ gat Pal j

an

( ANOl Number 2.

The potential for the presence of chemical reaction residues and other foreign material on fuel and storage cask components currently in dry storage should be assessed. I say the " potential" for the presence of material because although it is fairly certain that these Point Beach casks have residue it is not yet clear whether other cask systems would have unanticipated materials.

Additionally, the acceptability of any effects of the residue should be assessed.

i Number 3.

The cask evolutions introduced ionic zine and silica into the spent fuel pool.

Consequently, ionic zine and silica were introduced into the reactor coolant system from the spent fuel pool. Although tilis can be controlled, the amount of zinc and silica introduced and acceptability limits should be determined.

Likewise, for other cask systems any material introduced into the spent fuel pools which have a potential for entering the reactor coolant system should be assessed.

Number 4 The suitability of this.Daint,in other nuclear applications where exposure to boric acid is a potential should be re-reviewed. We have considered the effects of hydrogen generation in containment applications but a broader review may be in order.

Number 5 The adequacy of cask cleanliness controls should be assessed generically.

[The casks were not cleaned with water before immersion and soap was introduced during the decontamination process.]

i-I Third, I Evaluated the technical suonort by the vendor for the orevention ofsimilar events.

{

After the event, the ner, Sierra Nuclear, had an rations engineer onsite pro ' e technical expertise and ist in the unloading of the

k. Additionally, freque elepho conference calls were hel ith Wisconsin Electric sta and Sierra Nuclear A Jgners i lifornia to discuss technic issues. Additionally, sta from Palisades and

%ansas Nuc cat (other users of the cask) h participated in the telep conferences.

As Dr. Jankovich p iously stated, Sierra Nucl as developed a detail

' vestigation and

'on plan but also the d some deficiencies in im enting their design co of process.

Consequ we consider the tech (cal support provided by Nuclear for this ev to be adequate.

i

~

.. ~.

~.

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Aug-14-96 04:48P PBNP NRC Res idernt Office 414-755-4374 07 NIMS

/

' CONDITION REPORT cEE /M, d[

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g,

! rw:ription 30.

Gbo tikc 1I CJ*h'a 0

"'*eM 04 O G.

g (L.5 )cMr ha6 the pok^&)

b Iech

%*nc

"..M tie Si:P. d e ~-

3 l%i H - /}5Se skh"'""*f immed.

L4 leschcS.1%

te3f5 hue.

Shun At a D. [T.':

soak. e ne.

ens 6 c e le U *13 o.

5 FP 'rk c,6cea.f.r= %

_s ~

9Fppb.

sismitteen** (if otential g:<' sty or q "'% loses, siens enmeems and Mk p the R33 Manager or DSS) ~

P 2 he 15 Q,

four melhny

' nt theki S

Ab [kr}(93Mu'th is Ce@

les b i

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NP 3

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a fsCb ' cant 'lQJECMn Q

b*i Nup On fhe bel oo (MQg gQQ t'c "W _ _-;

Con =ctlye acticos complee9rl or la proTia ilj(1f a WO has been t.

ea>,.

ik. 9 'Fn w a or pois.,.

Q 95 g

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< h4 no crec hcAb r-S

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Lov melHn3 pnt meh.-

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Oppl.c Nahr, C d,.{^ A -)

eftC.f GM.kck tat %

Car %%'.n &

.. 4 a r.

uj eJt. n W*

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doY Sge b G G M.,6 rstd.WAf M AIG.

Recomm odauoos C o n h k 9.

C.wereA+

INw h*y &,

,ih6 c,., c(; @ c-e.ppj-M tuc Lthy pupses.

Th.s hswt vdI be casJ prior-to 5

placA %

fhe.

MS6 tnto 4hR. 5 Ff.

3 Izferczeca aisiator (Print namc/ dais) hA @. O _

Def,n,/S ELes / 7-:IM Hased dedher ao ase mesher.sto tJasemed andMessifer amabissed s

'RO Review Nose

"./.. DSF '- "% yasser @ is amarted yes.

a

~ % '. 9 uny systena. structurce, or compoucats inoperabic7 O No O Yes w

9 Further Evaluation Requirod.

f

-%i~

I the C00ditl00 reportable 7 (Ref. DCS 2.1.1 or 2.1.2)

O N.

Ov Further Evahastion Required A

Bh (SigE/Date)

Mame la work control centre CR beskat.

df/AAna sw w

y

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=.

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.: Manager Initial Review (Sign /Dess)

Plant Manager Closcout Review (Sign /Date) 1552 anon 0 06/24/94

____.--m__._._________

v Aug-14-96 04:4BP PBNP NRC Re s 1 cie rit Office 414-755-4374

'"t-'08 e

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@'fw/,5 n-I

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! STATU5: CLOSED UIllT: 0 ST5fgMs $F INITIATE 0s 07/11/95 CL0$80: 07/26/95 Msg #

,jM.

47tTIATOR: Otmult EVERS A0048mISTRATOR: SCOTT PFAFF i NupmER OF OPEN ACTIOles t o 199ut MellAGER: $(XITT PF)F ausg8R OF CLOSED ACTIONS : 1 TOTAL InsseER OF ACTIONS't Multi Astestpty seated Booket Costing ites Potentist tg Leech Zing Into the Sptfit fuCl P001 DESCRIPTIdelt wee

~

lt hee been dieeevered that the Cartmanic 11 coettne used on the nutt.eeeenesty seetess see l

~~

sterser hoe the setentist to teach sinc into the egent fust poe,t teien tasserseet. Lets teachehltity c ste ha day w.f the ase outd v4eid. erP sine ~~entreuen up to 5pp.

$fgnificences Zinc is a teu sueltfne point metet which fe controlled try leP 3.1.9 l

fus. essembties.

and hee the potentlet to ferti scale huitaiwp en 4

mote:

A aCs sinc injection ettely sereducted et Feeley reeutted in en asteepeeted easte buttehge en fust rede j

not have e specif teetten for ere sine sensentrattene. Cheetstry la surrently owelusting thle potentlet eendittet.

. %feettrighouse dose ove4essesen of 44 ase eseqstesed preer se any segg iesseny seetvtttto in me gfp gre geignonses j

fnte.

ITATue UPDATE:

(07/36/95 3AP) This Ca le belns closed hesed tgeen the sanctuelene of the evolustfort performed try Ch ansineertne (see post 95 04A0 for detalle). N -ry of the evetuotten con tre seen taider evoluetten et unde N e't "

enfatTyT*

ectlene taken for this inaue heve adequately addressed the oltuetten. This CA is belne closed bened upon i

othe ered completed.

u en i CittENES ST : SCOTT PFAFF

~

g, DATEe 07/13/95 i

treutATORT REPORTA4Lt.....(Y/4): Il T5 VIOLATION..............(Y/N): N TE LC0..................

N OPERA 31LITT EMPACT PER TI.(T/N)e W l

10 Cpn 21.................(T/w): W j

Mes agvigw..............

.(T/N):

JC0 4toulaEO............

{

.(Y/W); N 3CAe......................(T/N): N COMN!Tastu f............... ( T/w ):

s, l

0/ups n u l UPPDRTING DETERMINAi!DNS:

e a s e seem reportante event, currently westinghouse does not have any ser specificatione for sine concentra d

is net' W "

conducted try Cheelstry to determine whether there is en actual concern recording the buildup of sinc scale on

.AnevetustionIlebing In thJ 5FP. Pending the outcome of this Investigation ** edditionet coerective sneuures may be uerrented eaubtles

. g*.O 4EmplCC I2 FORMATION:

k 40e g NCta-0UTAGE

~C^*

i IQ_,,,,.

WUDOQ THtRD QUARTER OF 1995 E

47

. PtookSH WAe esof AseTictr4TCD tente ecslestCD I (AC: CIU 151RT RELATED

=~

! *$ttn 3rtNT futL COOLING end FILTRATION

)

1 i

j'FEtt:CES: hP 3.1.1 PeM 95 0460 1

I

.C.A 95-358 - _ _......ACT!0N tlupot.e.se..1 l

z

.: x i'

j as sus e4Tes er/ sins resseerve.tes

eat 2 e OP/13/tp Ott GC0ft NAFF enTemescue mRees t 1 RK DQuts R$CllVfDI 07/19/M CH FtLtr.lA heleittty FCLICIA pessNsEssY APPROVED
07/21/95 FELICIA MEINfESSFA E! PIED : 07/26/95 SCOTT PFAFF CLotto a 07/36/95 SCOTT PFAFF L

3 1 stunts tha potential ef fects that the Certoonic 11 M84 coating and teached Ilnc concentration in the Spent i si essemblite in the Spent Fuel Poet. Determine enr necessary corrective measures as appropriate.

ost egerve on j

e i 807/19/95 FPN) Received Actlen Inte ereups cet

[

! Responeltte Pereen FPW:FSLICIA II0lHISatY Ove Date: 07/31/99 i

i 107/21/95 FPit) cheeletry hee sempleted en ewetuotten of the use of sortealns es a primer for the M00s. This evet

/

j doenmented in PeM 95-0440. The evoluetten Cencluded titet White it le seceptable to use the ti.e Mete uhleh lie asinted trith cerherine, un should net une the eschemine point in the future ts11eoe ett surfaces pr11gg 1

ve elrse. u n i

Pesolue a ese use ad u-

. e-

- t s 6 4-. -.= -.. w ws e r enemissry netos to sainte the scen hgg siga enagjnt j

mee 6.

b A-.re.d en she poes. a t neon tevoto et atne are toen, ese need to ensure that the opent fust poet le ust i.

through the spent fust poet deelne mtit the sine to resueved. (An activity hee been plesed i rwy cQtated 4

ensure thle happene.) 2) fuel prior to releeding it in the core. 3) um need to ensure that cerbesinc coated with epony n the shutdeun resolutfeh.6 et to sultet>te etternettve.

4 oesn't teoch end/or find.e

.' (07/I1/95 PPn) Pessocf to SCOTT PFAFF for Verf fication.

9 (07/2&/95 149) DLA Ctesure ed 34.ai.

[

N evslust100 dissunsec In PeM 95 06&O have been reviewed and the renomseendetiene end sanctusta i

aatten leen 4 Chemierry tube) to destruf ne the zinc concentrattswie (and ensure that they are ecceptible) ha the teenefer e eeund..an posetutten List for the felt refueline outsee.

4 Ne additlenet actime are necessary et this time. Closed.

e o the Shutdown 4

dB

i -

.Au3-14.96 04:49P PBNP NRC Resident Office 414-755-4374

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COWITION RfPORT PAGEs

. of 9

ca 05 3ss 6Afs.

0'//26/96

%o

.sm. a s

.ame e i.

trer.cuers: Pen 95 0460 i

SIGNAftats cat

.............................................r.........st

.sgy leaue Manageet Dates

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Aug-14-9G 04249P PONP NRC Renident Of'1' i c e 414-755-4374 -

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~

NUCLEAR POWER DEPAR'INENT

~' g -

Screening Results IDENTIFIER (trkid)

CR 95_358 b

/

INITIATOR:

Dcr,

- DgutfIS EVERS S

..... - - _... - - - - - - -. - - - _ - - - - - - - _ - _ _ oURCE DOCUMENT DATE : 07/2lCClrs

__---... --. -- f_

SCREENING RESULTS:

(Y/N)

N)

Regulatory Reportable.....

H TS Violation............. @

10 CFR 21.................

N TS LCO..:.................

N Operability. Impact per TS.

N JCO Required..............

.N I

MSS Review................

N SCAQ......................

[N COMMENTS SUPPORTING SCREENING DETERMINATIONS:

This event is not a violation of any PBNP ?.:hnical Soecifications era.-

licer) sing commitment to the NRC and it i not a reportable.even ryently W2stinghousse dges not have an An evaluation la being conduc ed bvSFP e eci ications tor za.nc c nc.. acionb.e en en actual concern regarding t e bull up of zinc, scale on fuehem stry to determine w ethW2t:. re s

thn SFP. Pending the outcome of th:.s investigation -- additional corre.cn;s':::;n asse mansures may be warranted.

i:Crve

REFERENCES:

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SCREENED BY SAP -

7 SCOTT PFAFF

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Aud-14-90 04:47P P5NP NRC Resident Office 414-755-4374 I

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TO:

K.

R. Anundson P377 W. J. Hennestyy R. D.

Bronk N. L. Hoefert c.

A. Castell P377 FROM:

F. P. Hennessy D.

C. Ryggs M. G. Keshan P377 DATE:

July 18, 1995

SUBJECT:

USF, OF CARBOEINC PAINr As A PRIMER FOR TME MULTIAssmMBLY STomAss i

asANNTe E..,

REFEARHCE(4) e Eine injection in the Primary Systasa at the J. M. Farley Muclear '

Plant, by Prince Patton, presanted at the INPO Radiological (j

Prot ** tion Managgra MorXgnQp play 22-23. 199E An Engineering Assessment of Zine Ad'dition to PWR Primary Coolant

~

by Westinghouse Electric Corporation, SG-94-02-006, February 7'1'99,4Q COPY TO:

M.

F.

Baumann P377 M. K. Conry C

A. J. Cayim E. D. Schultz File R.

E.

Soisert On July 14, Dennis and Mark had compiled concerning the use of carboxinc paint 1995 Den spent fuel pool.

Our concern stame from the fact that in the the levels of sino and lead in the carborina paint are in excess of the levels allowed in NF 3.1.1 chemi a1 consamtmation control per corresten n,s1.etant Alleysi that while it its sancludsn is acceptable to use the two MSBs which have already been painted with carbozine, we should not use the carbozine in the future unless..i"~"

all surfaces primed with the carbozine paint receive a top coating of epox g i j (We are currently in the process of investigating the leachability of th carbozine with an epoxy topcoat.)

e This memo documents our review and analysia.

The carbozinc is used to coat the Multiassembly storage Basket will be innerset in the spent fuel pool.

(Nas) which While the carbosino outer surface o; I'"

the HSB is sealed with an epoxy coating, the arboninc on the inner sulface of the Man will be caractly CKDOStd to the acidic anvirnnmans ei r.nh f w

11,..e.m, usi soci. "

it is not intended for inanersion in acidic solutions.z.tseracure rrom the manuf to conduct laboratory tests for leachability.

This statement led us The tests showed that an b

uncoated carbozine surface will leach significant amounts of sinc into' y

colution when exposed to simulated spent fuel pool cooling water.

=

No. 55-0130 Calculation

~

iner.ama estimates that the level of sinc in the spent fuci pool will immersed in the spent fuel D001 for at houra.os ppb if th sosal uncontea surface of the c

"",~,,

time in much longer than we would actually expect,wkil. A 4s W i===rown 2

i t.

is would be oubmerged that long.

femmible tnat the MSB 7 4

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The limits set forth in MP 3.1.1 are in terms of contaminant neerial to be used itself.

levels in the in materials which are to be used in critical applications suchcinc and lead are limited coolant system or the spent fuel pool. The level of sinc in the carbosing' as the remotor paist is while the level of &ead as ggg peu noth matar a a

]

stainless steel compartment)eh w&11 he used streetly (ger nassanc.

e autrisants on aeur peeeeduwe gewes as well as materials which will be used u '-

indirectly (for exaspie, cleanaers to be used on a carbon steel comptEre'.M

-e which will contac*, secondary coolant which will then contact stainless se

.T.

components).

The limits in the procedure for low melting point metals' (1tuei

==,

sine or lead) are hosed on direet eenteess we taelude these limite en f

materials used indirectly to be ocaservative, e

accause 250 ppe is allowable for direct contact, the 95 ppb sinc level in the spent fuel pool will not be detrimental to corrosion rates of the apent fuel peel or any ceaponents in cd )

spent fuel pool.

The lead conoestration le 50 times less than CD9 31DC

._-a._,

. a %

,n, eyonc run pool w&1l Dt insignificant.

y, a,_

pool or in the reactor coolant system. Westinghouse has no specific limits on zine c

_m=:r.

In fact, one PWR (Farley) recently4 _ y '-

e fuel began injecting zine acetate into the primary, st reduce radiation levels in the primary system (Reference 1). coolant system in order to.g..u !'

i i

In order to

support the sinc addition at rarisy.

on primary system materials was performed (Reference 2).an angtneering assessmen a

i concluded that; zine levels of 10 The assessmenc l

Parley injected zine acetate into their primary coolant-40 ppb can actually reduce corrosion rates. -

months.

system for nine The zinc concentration in their primary coolant the zinc injection was successful at lowering outage dose rateswas = 40 ppb.

While ^

thick black scale was discovered on the fuel.

4

, an unusually conclusively linked to the sinc injection, an alternate explanation has notWhile this scale has j

yet been foune.

Until the Farley experience is fully evaluated, we eerseialy i

would not be willing to introdues sinc into the primary coolant system and subject it to high temperatures and pressure of power operation.

O zine borate, s

However.

I a possible precipitate in the spent fuel pool water. is m6*chtmor,e*

.e soluble at room temperature than at elevated temperatures.

temperature borate la (essentially spent fuel pool temperature),

In fact, at xcca t...

which would be eagseated due to teaching foem the unesated Addttionally. Farley injected siac for nine months, whereas the sine S'.h l

Mst.

one month due to removal of the sino by the spent fugl pool dem I

j Therefore, the sDent fuel in the pool will ka suP*=.4 ** the sine for less v

4 s.han' a.o percent et the time that the Farley fuel was. The combination of lower temperature and reduced contact l

not form on the' fuel in the spent fuel pool and that use of the existing Mstime leads with the uncoated carboxinc is acceptable.

E.'

To ensure that our conclusions transfer tube to insure that eine ingrese into the RCS is minimitedthe spe

correct, i

Addita==a11,

7 any previsualy irraalataa rual which im g

j cpent fuel poS1 will be visually inspected for unusual scale.asape.ed to minc in cne l

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.v ug-1C-C3 OC:47P PSNP NRC Resident Of'f' 1 ce C14-755-4374 03 (y

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PBM 95-0460 July 18, 1925 l

Page 3 f

  • 8 These mitigating motions are sufficient to allow use of the two MSB's whose internal surfaces are uncoated carborinc.

carbo 21nc is not acceptable in the lens erua for two reasone.However, use of the uncoated scale on the Parley fuel is conclusively emplained, sino atmuld continue to be First, until the.

treated as an undesirable contaminant which should be minimised.

35 ppb level of sino in the spent fuel pool will cause us Secondly,*a a s.a persens es our spees smet poea M altser, vale resta to mesa to exhaust expensive to replace and expensive to dispose of. Additionally, using the will limit our ability to use that same dominera11 er to remove co from the kWST.

Coating all carboxino surfaces with epoxy or finding a #

M suitable alternative primer will allow um to eliminate this logistical prob 1'e

.s. J and extend the life of our domine.

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Nuclear Power BusinessMnit Route Original to S.i.t.

J Report #

96-311

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_QAS to copy:

J moha-(assigned by QAS)

WORK MONITORINC RF' PORT J. Paltner. E. Schultre%o/h i

T. Jessessky, J. "Thot/crscri' '

P!le: Ql.1.I g ver: Sean P. McGinty Date: 5/22/95 Shift: 1 L.ocation of Activity: PAB Truck Access fwnnrnminarian A res Group Observed Work Document (s)

Functional Area Observation Program:

j Process #

Oroup Job Observation (GJO)

MTN WO # 9604669 Mansaement Job Observation (MJ0).

Other hP.7 Part 6 L98 Work Monitoring Report (WMR)h u:tiviry(s) Observed:

Nelding the ahiald lid during the second MSB loading.

2 ed Le arks:

Romarts showd peio, oeias for *=a senerna.aritum ram:4 aies

.)

[.{

L2. G.5) At the beginning of my shift, Malatenance had installed the automatic welding rig and laserted the sinms around'tfiMdlEld lid.

The welders bcEan by verifying the proper centering of the welding rig relative to the ID of the MSB. They also verifiedih@rrect witch lincup on the welding machine. Although they did not have a procedure that specified this switch lineup, they set up'.tjic ma' chine crrectly based on their knowledge of the process and then verified it by consulting with the welding engineer. After thes8c ecks they l

aantured an are on tha MSD and timed the travel of the welding rig through the arc to verify proper torch travel speed. ThedeIorted a I

-n:asured speed sli htly less than twenty inches per minute. Based on this speed the welding engineer told them to set their voltage to 31 6

' olts sad n observe a cu Tent limit of 350 amps. The welding engineer had this information on a hand written note which he had nrr -d from a verified table availabic in (bc welder's toolbox with tbc welding procedurcs. The wcldcrs then welded a test bcad y

stely ten inches long on a test coupon placed on top of the shield lid. All of their equipment operated properly within the

. eqw.. parameters during this test.

.2) Tbc welders used the automatic welding snachine to place tack welds about two inches long at each or the eightjo;nts where the birn segments met. Once they finished the tack welds, the welders used a pair of pilers to break off the taba that held the shims in place.

.2, 5.2,15.3) With the shima securely in ptsee to serve as a backing ring, the two welders set up the welding machine for the root pass.

They began the pass at about the 180* position. As they started the pass. the current rose to approximately 360 ampsgThe welder perrting the welding machine immediately recogniz.ed that he had exceeded his allowable cutTent and adjusted it to.3 Lamps.~~This took ive or six seconds and resulted in an area of tbc weld that had noticeable porosity. Maintenance documented this nocconprmance o_n CR

. 6-357. After completing the weld pass, one of the welders removed this area of the weld with a band grinder. This welder re,r--c-to so welding enginect that he observed a flame under the Srinding wheel which went out when he stopped grinding. The welders -

oncluded that residual solvent from c! caning and decontaminating the MSB caused the flame and resumed work. The observer ide te deenmmination area could not see the name because the MTC and MSD shell blocked thelt line of sight, After grindinr f' reldcd ever this acetion using the automatic welding machine.

.2) Foll: wing NDE of the root pas, the welders finished welding the shield lid using three passes with the automatic weldin inchine.

They remitned whhin their required parameters throuF.hout these passes.

ey Words: (Key words or phrans so be emered imo WMR database for word scarch.)

SFSI, MSB. Welding. CR 96-357. S-P-96-02 tecrptable Attributes Deficient Attributes:

g,

.3 Exceptional terrormance:

1.0 hiinor. Quicidr Corrected Ifems

.0 Fully Acceptable: G.3, 2.2.15.3 3.0 Less Significant Deficiency:

(CR/QCR Generation Necessary) 5.2

.I inally Acceptable:

4.0 Significant Deficiency:

(CR/QCR Generation Neceasary)

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n, R.6 A 4.tiver" t 2.3 Treintog A.Pyy****ECpahel'.h4c.r,..c C.! Sample Points R.7 A! ARA 2.4 QA Requittments 12.3 Callhfasion

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C.4 Clsendci Conaut Program S.1 Post. Manning 3.2 Design %

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3.2 accurley $quipmem 3.3 Teseovery Modificesions 13.2 Sassage i

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l Fire Prntactica T. ) I!ossdag/ Rigging 4.3 D~.~ntation Requirernents 14.3 Operat on S-sev h..j-j F.I Combumble Sanrage T.2 Environmental CondJoons 44 Record Storage

-i.~TihCaEdloon~ Reports.

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15.1 Norconformances locnofled i

E3 FP Equ'pasons laepsea.an T.4 Proa.caive Equipmani/Ue3Be 5.1 Work'Insw/pme/Drwg Adequacy 15.2 Cond.tions beefwd.-

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,ctner Penetranons T.7 Posmans of People 6.1 Work Instr /ProuDrwg Approval 15.5 CRs Disposinoped

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T.8 Tools & Equapmsa 6.2 Work lasta/ Proc /Drwg Control

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Corumi 16.1 Timely Responses 3.2 Managenunt Oversight T.10 Electncal 6.7 Tempnrery Prncedure Comrol 10.2 Treading 13 Work Planrung T.!L Fall Protecoun 6.8 Work Closcout Documentanon 16.3 Acdon Prevent Recurrence 14 PrsJob linefang

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1.9 Comma:x!/Connel 4.1 So!!! Kits 5.2 Matena! T11gmg 18.1 Audit ?heule Q

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1R.2 AQCQUACy of AIM 11U **'

3 il Concuirm Checks 2.3 Eye Wash 9.1 Personnel Qualificanon 18.3 Atidit Cheeksist Use *G I 12 Puudub Dnering Z.4 Asbestos Corurol 9.2 Procedure Quahficauon

. General Operatio~ns -

Plant Canditnans.

Z.5 Gas Botde Storage 9.3 Weld laspeedon X.! Other

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From: Mary Carpenter May 28,1996 Wisconsin Electric suspends loading of spent fuel containers after combustible gas causes brief gas burn TWO CREEKG, Wis. - Loading of spent nuclear fuelinto dry storage containers was suspended at Point Beach Nuclear Plant after combustible gas was detected and caused a brief gas burn during a welding procedure early this mornin0 Fuel assemblies had been placed into a container and removed from the spent fuel pool. While a shield lid was being mechanically welded to the top of the container, combustible gas was detected and a brief gas burn occurred. Point Beach employees diccontinued the welding procedure. No one was injured and there was no risk to the general public. The occurrence did not result in any release of radiation.

  • We are conducting a thorough investigation and we will not resume loading spent fuel until we have a clear understanding of the cause of the gas bum," ocid Bob Link, vice president of nuclear power for Wisconsin Electric. "We will thoroughly review all of the related information to determine the root cause of this mornin0's occurmnca.'

Plant employees previuusly luaded two containers successfully, one as decently as last week using the same loading process. These containers are now located at the dry cask storage facility on the plant site.

Spent fuel has been safely managed at Point Beach since the plant went into operation in 1970. However, the spent fuel storage poolinside the plant is becoming full, and additional storage capacity is necessary for the continued operation of the plant.

Wisconsin Electric Power Co., a subsidiary of Wisconsin Energy Corp., provides electn*c natural gas and/or steam service to about 2.3 million people in snuthenstem Wiscansin (including the Milwaukee ama), the Appleton nmn, the Prairie du Chien area, and portions of northeastern Wisconsin and Michigan's Upper Perrinsule.

ll##

is/d

l May 28, 1996 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE PN0-III-96-033 This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information is as initially received without verification or evaluation, and is basically all that is known by Region III staff (Lisle, Illinois) on this date.

Facility Licensee Emergency Classification Wisconsin Electric Power Co.

Notification of Unusual Event Point Beach 1 2 Alert Two Rivers, Wisconsin Site Area Emergency Dockets: 50-266,50-301 General Emergency X Not Applicable

Subject:

UNIDENTIFIED GAS IGNITED DURING SPENT FUEL CASK WELDING At 2:45 a.m. (CDT) on May 28, 1996, an unidentified gas ignited inside a dry cask spent fuel storage container during initiation of welding the shield lid inside the container. The container had been loaded with spent fuel and removed from the spent fuel storage pool. The gas ignition, which was heard and observed by plant technicians, displaced the shield lid, leaving it in place but tipped at a slight angle -- with one edge about 1 inch higher than normal. The shield lid is 9 inches thick and weighs about 4,400 pounds.

The VSC-24 cask was removed from the spent fuel storage pool about 4:10 p.m. on May 27 and placed in the cask decontamination area in the auxiliary building. The cask remained filled with water, and about 30 gallons was removed to create an air space under the shield lid. A welding machine is used to weld the shield lid in place. The gaseous ignition occurred during initiation of welding, but before any welding took place.

There was no evidence of any damage to the spent fuel in the cask qs a result of the gaseous ignition. ContinuoJs air measurements in the cask decontamination area showed no measurable radioactivity. There were no injuries.

The licensee is investigating the incident and is attempting to identify the gas which ignited. After a preliminary investigation, the licensee plans to return the cask to the spent fuel storage pool for further examination. The licensee is continuing to monitor for radioactivity and combustible gases.

The NRC senior resident inspector responded to the plant site after being notified of the event and is continuing to monitor the licensee's activities. Additional inspectors are being sent to the site from the regional office.

4;,oM40pW pg.

b

. ~ _

.. _.... = _ _. _ _ _.. _ _ _. _ _.... _ _ _ -. _ -. _.

I PNG-Ill-96-033 !

L l

This is the third VSC-24 cask loaded by the licensee. The other two casks have been placed on the outdoor storage pad. Each cask holds 24 fuel assemblies, l

The-licensee plans to issue a news release. The State of Wisconsin will be notified. The information in this preliminary notification has been

-reviewed with licensee management.

Region III (Chicago) was notified of this event by the resident inspector at 3:40 a.m. on May 28, 1996. This information is current as of 10 a.m.

on May 28, 1996.

Contact:

TIMOTHY K08TEZ MARTIN FARBER (414)755-2309 (708)829-9605 4

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5, sos wannENwuE ROAD g

ustE. K.UNotS 80632-4355 May 29, 1996 MEMORANDUM To:

Roy J. Caniano, Team Leader

. Augmented Inspection Team (AIT)

Point Beach Nuclear Plant FROM:

John A. Grobe, Deputy Directo Division of Reactor Safety

SUBJECT:

AIT CHARTER FOR POINT BEACH DRY CASK EVENT On May 28, 1996, a gas ignition event occurred during dry cask activities at the Point Beach Nuclear Plant. Based on discussions with the Offices of Nuclear Reactor Regulation, Nuclear Materials Safety and Safeguards, and Analysis and Evaluation of Operational Data, and on initial inspection findings regarding the event, an AIT has been chartered in accordance with NRC Inspection Manual Chapter 0325 (e.g., significant or unexpected system interaction).

Attached for your implementation is an AIT Charter for the inspection of the i

dry cask gas ignition event of May 28 at Point Beach.

The objectives of the team are to identify and communicate both'the facts of the event and any generic safety concerns, and to document the findings and conclusions of the onsite inspection.

Should you have any questions regarding these objectives or the attached Charter, please do not hesitate to contact me.

Attachment:

AIT Charter cc w/att:

J.-M. Taylor, EDO G. H. Marcus, NRR J. L. Hilhoan, OEDO C. J. Paperiello, NMSS H. L. Thompson, OEDO W. O. Travers, NMSS H. J. Miller, RIII C. J. Haughney, NMSS A. B. Beach, RIII E. J. Leeds, NMSS W. L. Axelson, RIII E. L. Jordan, AEOD l

G. E. Grant, RIII R. J. Barrett, AE00 C. D. Pederson, RIII

8. C. McCabe, OEDO W. T. Russell, NRR A. J. Kugler, LPM /NRR R. E. Zimmeman, NRR A. G. Hansen, LPM /NRR J. W. Roe, NRR T. J. Kobetz, SRI

% D i uv^i4 4/.

mm t 91 s. c:7.1770

1. Me I r4

.FROM'; Panasonic PPF Auomented Insnection Team Charter - Point Beach Nuclear Plant l

Examine the circumstances surrounding the dry cask ignition event at the Point Beach Nuclear Plant on May i

28, 1996, including but not limited to the following:

1.

Develop and validate a chronological sequence of events and activities for the dry cask evolution, detailing events just prior to and immediately after the gas ignition.

2.

Compare this sequence of events to other dry cask loading evolutions at Point Beach to identify any anomalies associated with this particular load.

3.

Evaluate the licensee's actions during and followin the event; including their immediate response to the event, is lementation of emergency plans and management response. procedures, event reporting, fo lowup actions, and 4.

Evaluate the extent of the licensee's analysis and determination of the root cause for the event, including potential source (s) of hydrogen generation, and the initial evaluation of appropriate corrective actions.

5.

Determine if appropriate attention was given to the condition of systems and components associated with dry cask evolutions, including compatibility of the dry cask with spent fuel pool conditions.

I 6.

Determine any potential generic implications of the event.

Evaluate the technical' support by the vendor for the prevention of similar events.

7.

Evaluate the adequacy and appropriateness of radiation protection.

precautions taken by the licensee as part of the dry cask loading activity.

8.

Evaluate the radiation protection consequences of the event to both the plant staff and the general public.

i I

i

i uno-

4 INTERNAL i

CORRESPONDENCE e

PBM 96-0320 To: C. A. Castell B. D. O'Connell S. A. Pfaff S. J. Zepplin

'~

Frean:

G. J. Maxfield 4

Date: May 29,1996 3

Subject:

INCIDENTINVESTIGATIONII 96-01 BRIEF COMBUSTIBLE GAS BURN DURING DRY STORAGE CONTAINER SHIFTD LID WELDING i

Copy To: R. E. Link W. B. Fromm T. C. Guay G. J. Maxfield j

J. G. Schweitzer R. D. Seizert T7A.3 At approximately 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> on Monday, May 28,1996, during initiation ofwelding the shield i

lid inside the third dry fuel storage container, an unidentified combustible gas briefly igni l

ignition slightly cocked the shield lid. Continuous air measurements in the cask decontaminat 3

area showed no measurable radioactivity. There were no personnelinjuries as a result of this event. An initial activity plan focused on notification of the NRC resident inspector; determination ofimmediate reporting requirements; identification and monitoring of the source

i the gas; removal of the shims and replacement of the shield lid; and preparations for rel d

loaded container to the spent fuel pool I would like you to participate on an incident investigation team to review this event. T of the investigation should include:

Determination of the root cause(s) of this event using Taproot root cause tec$iiques.

s.

o Identification of the source of the gas.

o A review of welding procedures, processes, and work practices, includiag purging o

welding as is the normal practice for primary side welding activities, positioning of the person performing the welding and sampling for combustible gases.

An evaluation ofoperating experience at other utilities using the VSC-24 multi-asse o

. scaled basket and with CarboZinc coating.

A review ofprecursors to this event. The precursors may include, but not be limited to o

previous evaluations of the protective coating and experiences during the loading of the previous two containers.

N/Y 9e?Mora y

~-... -

I May 29,1996 Page 2 Mr. Castell is appointed chairman of this incident investigation team. It is anticipated that scope of this investigation will not need to be more broad then detailed above; however, shou the team believe that the scope needs to be changed, this should be discussed with me. I anticipate that this investigation can be completed by Friday, June 7,1996, The investigation should follow the instructions provided in procedure NP 5.3.3, " Post-Inc 1

Critique and Investigation." Thus, your team will prepare a report ofyour investigati and will present your report to the Manager's Supervisory Staff. The report shoul Friday, June 14,1996.

G. J.

eld Plant Manager l

,e I

i

9 Ff tan: OEce of Pubhc Mars Ts: 58Wid Pt Beach Date:F29/96 Tirne:C:18:12 Page 1 of 2 b-U.S. NUCLEAR REGULATORY COMMISSION Region III Office of Public Affairs 801 Warrenville Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT:

RIII-96-21 May 29, 1996 CONTACT:

Jan Strasma 708/829-9663 Angela Dauginas 708/829-9662 E-mail:

crpa30 nrc. gov NRC SENDS AUGHENTED INSPECTION TEAM TO REVIEW GASEOUS IGNITION INCIDENT IN SPENT FUEL CASK AT POINT BEACH NUCLEAR PLANT The Nuclear Regulatory Commission staff is sending an Augmented Inspection Team to the Point Beach Nuclear Power Station to review the unexpectect burning of a combustible gas during the welding of a lid on a spent fuel storage cask early Tuesday.

The Point Beach plant, located near Two Rivers, Wisconsin, is operated by Wisconsin Electric Power Cornpany.

The storage cask had been loaded with 24 spent fuel assemblies and moved from the spent fuel storage pool at the plant to an adjacent work area.

As technicians began welding a-4,400 pound lid on the container, combustible gas inside the container ignited.

Pressure from the burning gas moved the lid slightly, leaving it about one-inch out of place.

The cask was filled with water at the time of the incident with a small air space at the top.

The utility stopped the welding proceduro and is now investigating the cause of the gaseous ignition.

Air monitors showed there was no roloaso of radioactivity from tho container, and there is no evidence of damage to the spent fuel.

No one was injured in the incident.

Both reactors at the Point Beach plant were operating at the time and were not affected by the incident.

Members of the NRC inspection team will join the NRC Senior Resident Inspector whc went to the plant early today Tuesday to monitor the utility's a.ctivities.

The team members are from j

the NRC's Region III off:.co in Lisle, Illinois, and the NRC's l

Headquarters in Rockville, Maryland.

6/M

from: Ofrwe of Pubbc Apars To: $RMtlPt Beach Dde:W29/96 Tane:08:19:16 e

Page 2 ef 2 S

^

The team will review the incident and monitor the utility's investigation.

At the ceanpletion of its onsite review, the inspection team will present its findings to utility representatives in a meeting which is open to public observation.

The schedule and location of the mooting will be announced later.

A written report of the inspection findings will be issued several weeks after the conclusion of the inspection.

This was the third spant fuel storage cask loaded at the Point Beach facility.

The other two were loaded without incident and placed on an outdoor storage pad.

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A gas emplestem inside a higtr level naclear 1 smote silo at Wisconsist Electric Power DeM's (WESCO) Point femah Emaclear Flast has aw w'==== man's rarot =r ~g

' anclear weste deep for the seceand time la five ansatans.

" tham is the first medianotive weste stowere euspissiest at a U.S. meclear plass, seis Devia Meczist, wtwo Dimeetese of the citisees* Uttitty sense (CIB).

att's time for IEEPCO to stop eag.a7-- = e== =ith moel er weste on san. =:-=< s==,

said w et.

Assesding to the meelear hogalatexy camadssion M) imittel at 2:45 a.m. on aqr 24th, an insiaantified gas. ignited a its11 -Leaded etek of *=e1L==se temste===8 =<=seg 14 team of asi 3

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==*ing an emplosion. the esplosion eccurred gast s

pei*e to the welp the 9 i" *S *-goesk lid that tseiple ehest.

4, The d'ide 'tne Lited tape 2 ten lid, Leeving it tipped at a with 1 lack higher than mosam1. emere =enee no injuries.

WEFC0 has suspended fasther 1"<i of anclear - waste cayks

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tantil it can dee-t== the cease of the m arf atant and whether may spent reel aves woes eessaged er taas ensplostem. Each 18 foot higts cask is imeded with 14 toes of medicestive waste, incloding 170 pommes of plutantum.

Eena leessa maio contains the musiyaient sedioeotivikr of 340 Bir== nema-type emiplestems.

&oomaining to Fedasal guidelines, the weeto mest he )suyt safe far 10,000 years,.

om o.oeme,es as, isss, amo. < a-arr cirsuit' co==s audse mark Frankel ekset down the panleau weste eng far the first time. Judge teamhmL ruled that the minblic servios Commission's (PSC)

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to consider how tems waste mer need to be stored in 1riscoasta und l

did not, pumpemely evelmuste enamonio enesgr alteamstives.

The PSC on May 20th Leeemd its use emeer roependay the daup.

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It's amo mese season to keep ear sados Michigan sheseline from beoontag a deseoto yemmament neclear weste Gump," esmoloded marriet.

i cut win be eekaar fee em immediate Fac 1 wM7 +'en and ma esses svvessaame unear zoom-L Mica to racpen the dump.

  1. M For amore infaamet. Lea, contacts 10mpid Hasseitt (808)-251-3322.

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95/89/96 31:38 T1/RX No.0645 P.001 g

TOTR. P.02

T 4

NRC AIT ENTRANCE MEETING MAY 30.1996 Attendancs Wisconsin F,lectric Power Company R. E. Link Vice President-Nuclear Power (by telecon)

G. J. Maxfield Manager-PBNP G. M. Krieser Manager-Industry & Regu!atory Services S, A. Patuiski Manager-Nuclear Engineering A. J. Cayia Production Manager W. B. Fromm

. Manager-Site Engineering D. D. Schoon Manager-Chemistry M. F. Baumann Manager-Nuclear Fuel Services J. A. Palmer Manager-Maintenance P. B. Tindall

- Manager-Health Physics T. C. Guay Manager-Regulatory Services J. A. Holmes Training Coordinator E. J. Epstein Acting General Supervisor-Health Physics T. J. Jessessky Senior Project Engineer-Site QA

. T. G. Malanowski Senior Project Engineer-Licensing F. A. Flentje Regulatory Specialist

{

Root Cause Evaluation Team C. A. Castell(Team Leader)

Senior Engineer-Licensing -

i S. A. Pfaff Senior Engineer-Operating Experience S. J. Zepplin Training Specialist B. D. O'Connell Senior Engineer-Systems Engineering Sierra Nuclear Cornoretion T. McNulty i

i i

1 4

Nuclear Regulatory Commissian R. J. Caniano (Team Leader)

Chief, Plant Support Section #2, DRS, RIII T. J. Kobetz Senior Resident Inspector R. Laufer NRR Project Manager-KNPP R. Paul Reactor Inspector-RP, RIII J. Davis C. Withee

(

l

INTERNAL

' CORRESPONDENCE I

PBM 96-0329 To: W. J. Hennessy A. J. Cayia C. A. Castell E. J. Enste:n M. F. Baumann From: G. J. Maxfield i

Date: May 30,1996 1

Subject:

NRC AUGMENTED INSPECTION TEAM (AIT) copy To:

W. B. Fromm G. M. Krieser T. G. Staskal G. J. Mrsfield i

P. B. Tindall.

T. C. Guay T. G. Malanowski R. E. :d i

Al.4.1 1

An entrance meeting was held today between NRC and NPBU representc:i.

augmented inspection team (AIT) effort which commences today and is e,.;

approximately one week.

The NRC team members and areas of expenise are: '

i i

Roy Caniano (Team Leader and Chief, Plant Support Branch 2, Division e'

P Safety, Region III).

Ron Paul (reports to Mr Caniano and will address radiation protenu consequences).

Tim Kobetz (PBNP Senior Resident Inspector)

Jim Davis (NRC headquaners, Ph.D. in metallurgy, will address materich it: 0 Rich Laufer (NRR Project Manager for Kewaunee Nuclear Power Plant)

Carl Withee (NRR, areas of expenise include shielding, criticality safety; w','

addressing fuelissues)

Paul Narbut (former resident inspector in Region V, NRR Vendor Brr nd.;

vendorissues)

%T9000 W.

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May 30,1996 1

l Page 2 i

1 The eight areas which will be the focus of the AIT, the NRC team assignment, and the WE lead individuals are:

l.

1.

Chronological sequence of events prior to and immediately after gas ignition.

(Kobetz/Cayia) 2.

Comparison of sequence of events to other cask loadings, identifying similarities and -

differences. (Withee/W.Hennessy) i 3.

Evaluation of actions during and following event (including EP event categories, other notifications, etc.) (Kobetz/Cayia) 4.

Analysis of event (root cause evaluation) and corrective actions. (Davis /Castell) 5.

Appropriate attention to system and component interfaces, including compatibility of cask with spent fuel.- (Narbut/ Wood)'

(Duane Schoon will address chemistry-related areas) 6.

Generic implications of event, including notifications made by vendor to other users of cask. (Davis and Narbut/Baumann)-

7.

Adequacy of overall radiation protection precautions. (Paul /E. Epstein) 1 8.

Radiological consequences of this event. (Paul /E. Epstein)-

G.J.M eld Plant Manager i

l l

l t

l

05/30/96 AIT/PBNP CONTACT LIST NRC PBNP Ext #

1.

Kobetz Cayia 6668 2.

Withee Hennessy 6573 3.

Kobetz Cayia 6668 4.

Davis Castell 6132 (through 06/01 TSC-A (06/03-End) 5.

Narbut Wood 6317 Schoon (Chem) 6680 6.

Davis /Narbut Baumann Page or 6221 i.

7.

Paul Epstein 6228 8.

Paul Epstein 6228 Other Contacts 1.

Fritzie Flentje 6221 2.

Terry Guay (Reg Services Mgr) 6430 3.

Greg Maxfield (PBNP Manager) 6212 f

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UNITED STATES NUCLEAR REGULATORY COMISSION

. OFFICE-0F NUCLEAR REACTOR REGULATION r

WASHINGTON, D.C.

20555 l

l May 31, 1996 l

l NRC INFORMATION NOTICE 96-XX: HYDROGEN GAS IGhiTION DURING VSC-24 MSB CLOSURE-WELDING l

Addressees All holders of operating licenses or construction permits for nuclear power reactors.

Independent spent _ fuel. storage installation designers and fabricators.

l i

-Purpose l

The U.S. Nuclear Regulatory Commission (NRC) is issuing this information l-notice to alert addressees to a hydrogen gas ignition event which occurred during the welding of the shield lid on a spent fuel storage cask at the Point Beach Nuclear Power Plant.

It is expected that recipients will review the information for. applicability to their facilities and consider actions, as appropriate, to avoid similar problems.

However, suggestions contained in this information notice are not NRC requirements; therefore,;no specific action or written response is required.

Description of Cirggastances

.e u

l On'May.28, 1996, a hydrogen gas ignition occurred during the welding of-the; j

, shield lid on a VSC-24 MSB (multi-assembly sealed basket).

The gas ignition displaced the shield-lid, leaving it in-place but tipped at a slight angle, l

with one edge about-= ir.d higher than normal.

~3 tuema L

The VSC-24 MTC (multi-assembly transfer cask), a shielded lifting device I

utilized to transfer the MSB loaded with spent-fuel to the VCC (ventilated concrete cask) for storage, had been placed-in the cask decontamination work area in'the auxiliary building. 'Approximately 30 gallons of spent fuel pool water had been drained to facilitato shield lid welding by creating an air space below the lid. The hydrogen gas ignition occurred during the-initiai. ion of-the shield lid welding, approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after the loaded MTC had been removed from the spent fuel storage pool.

Discussion Following the event, gas and water samples collected from the MSB internals showed detectable levels of hydrogen in the air space beneath the shield lid and dissolved in the MSC water. -The licensee then continuously purged the air space beneath the lid with nitrogen to prevent the accumulation of' combustible i

gases, and moved the shield lid back into its original position.

The MSB was then fully flooded.to eliminate the air space under the shield lid, and transferred back to the spent fuel storage pool. The licensee unloaded the spent fuel assemblies and placed them_in the spent fuel pool storage racks.

l

P

, u The'MTC/MSB was subsequently moved back to the decontamination work area for j.

further inspection as part of the licensee's investigation of the combustible gas burn.- A visual examination of the spent fuel assemblies, MSB and MTC

~

showed no evidence of damage as a result of the combustible gas ignition.

'The investigation into the possible sources of hydrogen is. focusing on a zinc-based coating applied to the internal surfaces of the MSB. The zinc may have reacted chemically with the acidic water from the spent fuel storage pool to produce hydrogen. A minimum boron concentration is required to be maintained, j

as a criticality control, in the spent fuel storage pool water at Pressurized WaterReactors-(PWRs),

i An NRC Augmented Inspection Team (AIT) has been formed and is on-site to investigate the event.

The objectives of the AIT are to identify and i

connunicate both the facts of the event and any generic safety concerns, and to document'the findings and conclusions of the on-site inspection.

i i

4 e

I i

i 2

j j

4

IN 9X-XX Month XX, 199X Page X of X Related Generic Co-inications (An optional list of other generic communications that have previously addressed the subject of the information notice.)

This information notice requires no specific action or written response.

If you have any questions about the information in this notice, please contact (one of) the technical contact (s) listed below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.

l I

Brian K. Grimes, Director Division of Operating Reactor Support Office of Nuclear Reactor Regulation Technical contact (s):

Attachment:

List of Recently Issued NRC Information Notices

, jut 4-03-1996 11:30 SIEPRA iUCLEAR COPP 408 438 52c5 P.02 tb Oh u

q 6/3/%

SELECTION OF CARBO ZINC 11 l

FOR USE IN COATING MSBs l

i MSBs require coating to protect the spent fuel pool from corrosion e

products of the carbon steel shcIl and internals.

An evaluation was completed in 1990 of available coating materials that could meet VSC operational requirements.

  • Resistance to radiation.

Maintain intergity at relatively high 700'F temperature inside MSB.

Using all information sources available at the time including paint e

vendors, operators ofnuclear power plants, and relevent nuclear industry i

experience, zine based inorganic coatings were selected.

)

Carbo Zinc 11 e

Dimetcote 6

=

Carbo Zinc 11 was selected because it was extensively used in the nuclear industry and significant testing confirmed its performance.

Carbo Zinc 11 was the only coating approved for use in the Palisades spent fuel pool at the time of coating selection.

Main focus of selection involved performance in the spent fuel pool.

Discussions with several nuclear organizations did not identify concerns with hydrogen generation due to contact with spent fuel pool water.

Hydrogen generation in a closed spent fuel cask filled with fuel pool water was never identified as a concern.

I l-l Ahf

^

~ JL2K$3-1995~11:38 SIERRA IU1. EAR CORP 408 438 5206 P.03 SELECTION OF CARBO ZINC 11 FOR USE IN COATING MSBs (Continued)

Until incident at Point Beach, SNC was not aware of any combustible e

gas concerns with the VSC.

SNC has put together an action plan to address hydrogen generation e

within the MSB during loading operations.

  • Preliminary conclusion is that procedural changes will eliminate the potential for combustible concentrations of hydrogen being present during MSB closure operations.

4 i

O w

JUi-ONiW6 11!38 SIEPPA FUCLEAR COPP 408 438 5206 P.04 t

RELEVANT DIFFERENCES IN LOADING PROCEDURES PALISADES VS. POINT BEACH 5

Point Beach Vent in shield lid closed prior to and during welding.

30 Gals. of water pumped out prior to welding shield lid.

e Amount of water pumped out determined by pumping time.

MSB #3 sat for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after pumpdown prior to start of welding.

Appearance ofloose Carbo Zinc on surface of spent fuel pool.

Increases potential for hydrogen generation Shims for shield lid installed using pneumatic tool (tighter fit).

Palisades 4

Vent in shield lid open prior to and during welding.

  • Slight negative pressure created in air space prior to and during welding.

75 gals. of water pumped out prior to welding shield lid.

e Amount of water pumped out is measured.

Lid welding activities started immediately after pumpdown.

e No appearance ofloose Carbo Zinc on surface of spent fuel pool.

Shims for shield lid installed by hand (looser fit).

'3

w es-issi '111.59 stERRd thiNUN CORP 408 38 5206 P.OS j

RECOMMENDED ACTIONS TO PREVENT RECURRENCE Follow approach used in 13 previously successful loadings at Palisades.

Assure loose Carbo Zine is removed from interior of MSB.

Pump out at least 75 gals. of water prior to welding shield lid.

- Measure amount of water pumped out to assure accuracy.

Keep vent in shield lid open until water is completely removed.

Maintain slight negative pressure in air space prior to and during welding.

l Check for combustible gas in area of welding prior to start of

=

welding.

i Start shield lid welding activities immediately after pumpdown.

TOTAL P.05

m O

c.

MarissaBailey(MGB))Nfdbb'.RASI From:

. NCD2. CHI.' JAG, ARDl.ARPl TD:3 A 680% M

- To:

i Date: Monday,= June.3, 1996 11:57 am i

Subject:

Draf t -CAL for the VSC-24 1

I Attached, in WP5.2 format, is-the draft CAL for the VSC-24 cask users.

Comments from Hugh Thompson and 0GC have already beer incorporated.

j d

We did not add a sentence stating that NMSS will provide support to the Regions.

If the Regions feel this is necessary, please suggest some wording.

j We would like.to assure you that NMSS/SFP0 will support the Regions in resolving the issues in the CAL.

- The Office of Public Affairs at HQ is planning to issue a press release upon issuance of the three CALs.

Please contact Eric Leeds at (301) 415-8540 when~

' i 3

the CALs have been issued.

If you have any questions, please contact'me at (301) 415-8531 or Eric Leeds.

Thank you, l

CC:

NCD2.ARI.KMK, NCD2.CHl.TJK1, NCD2.CHl.MEP, EJL, CJ i

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6/3 9:15 am i

CAL No. X-XX-XXX Consumers Power. Company Wisconsin Electric. Power Company Entergy Operations', Inc.

SUBJECT:

CONFIRMATORY ACTION-LETTER

Dear Sir (s):

.j On June XX, 1996, representatives from NRC Headquarters, Regions III & IV and your company held a conference call to discuss your use of.the Pacific Sierra Nuclear Associate's Ventilated Storage Cask (VSC)-24 system. We initiated the conference call as a result of the May 28, 1996 event at the Point Beach Nuclear Plant involving a VSC-24 spent fuel storage cask. During the Point 1

Beach event, a hydrogen gas ignition occurred'during the. welding of the shield j

lid ~on a VSC-24 multi-assembly sealed basket.(MSB). The gas ignition displaced the shield lid, leaving it in place but tipped'at a slight. angle.

j The VSC-24 multi-assembly. transfer cask (MTC), a shielded lifting device used to transfer the MSB loaded with spent fuel for storage, had been placed in the

- cask. decontamination work area in the auxiliary building. Approximately 30 gallons of spent fuel pool water had been drained to facilitate welding of the shield lid by creating an air. space below the lid.. The' hydrogen gas' ignition occurred during the initiation of the shield' lid welding, approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after the loaded MTC had been removed from the' spent fuel storage pool.

Although the gas ignition caused no injuries.or radiological releases and no 8

(

damage to the spent fuel or to the VSC components, the staff is concerned that such an event has not been evaluated and could potentially result in more severe consequences. Therefore, on May 29, 1996, an NRC Augmented Team Inspection (AIT) was formed and sent to the site to investigate the event.

The objectives of the AIT are to identify and communicate both the facts of the event and any generic safety concerns and to document the findings and conclusions of the onsite inspection.

Pursuant to a telephone conversation between (names and nositions of orincioal individuals reoresentina the licensee) and (names and nositions of *orincioal individuals reoresentina the NRC) on (date)

, it is our understanding that you have'taken (or will take) the following actions prior to loading, or unloading, any spent fuel in a VSC-24 cask or placing a VSC-24 cask into the spent fuel pool:

(1)

You will have assessed the potential for the generation and ignition of explosive gases during.all phases of operation of the VSC-24 system-i (2)'

You.will have compensatory actions in place to minimize the potential

'i for the generation and ignition of explosive gases; (3)

You will have in place procedures to respond in the event of a gas ignition and the applicable personnel trained and briefed accordingly; and i

~.

M (4) 14 days prior to loading, or unloading, any spent fuel in a VSC-24 cask, D[

the applicable plant personnel will contact the Director, Division of Reactor Projects, (applicable Region).

y Pursuant to Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, you are k'

required to:

l 1)

Notify me immediately if your understanding differs from that set forth above; 2)

Notify me if for any reason you cannot complete the actions within the specified schedule and advise me in writing of your modified schedule in advance of the change; and 4

3)

Notify me in writing when you have completed the actions addressed in this Confirmatory Action Letter.

Issuance of this Confirmatory Action Letter does not preclude issuance of an order formalizing the above commitments or requiring other actions on the part of the licensee; nor does it preclude the NRC from taking enforcement action for violations of NRC requirements that may have prompted the issuance of this letter.

In addition, failure to take the actions addressed in this Confirmatory Action Letter may result in enforcement action.

l The responses directed by this letter are not subject to the clearance procedures of the Office of Nanagement and Budget as required by the Paperwork Reduction Act of 1980, Pub. L. No.96-511.

I In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its enclosure ((s), and your response will be placed in the NRC 3

Public Document Room (PDR).

To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.

Sincerely, Regional Administrator (or designee)

(Director, NRR) (or designee)

(Director, HMSS) (or designee) l Docket No.

License No.

nr./xf1T~ksu ID:7085151096 JUN 04'96 9: 47No.bb2kO1 o

o NOTE FOR ROY CANIANO:

Here's the draft announcement on the meeting-Any comments?

Jan e-mail: rjs2 g/a /Ja* #w phone: 708/829-9663 i

I

- ~- ur:c/ rrn r:my - - - -

igfygg g g g-gg,,g4 96 9: 47 r40,002 p,02 i :

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- DRAFT -

U.S. NUCLEAR REGULATORY COMMISSION Region III Office of Public Affairs 801 Warrenv111e Road, Lisle IL 60532-4351 NEWS ANNOUNCEMENT:

RIII-96-23 CONTACT:

Jan Strasma 708 June 4, 1996 Angela Dauginas/829-9663 i

708/829-9662 E-mails opa30nrc. gov 4

i NRC SPECIAL INSPECTION TEAM TO PRESENT FINDINGS OF OF GAS BURN IN SPENT FUEL CASK AT POINT BEACH NUC i

will meet Friday _A Nuclear Regulatory Commission Augmented Inspection Team officials to discu(June 7) with Wisconsin Electric Power Company i

burn in a spent fuel storage container May 28 at the Point Beachs Nuclear Power Station.

Wisconsin.

The Station is near Two Rivers, The meeting will be-at 10-a.p.m. in the Two Creeks Town Rivers, Wisconsin. Hall, located at State Highway 42 and Tapawingo Road north of T i

i The six-person inspection team is headed b 4

l Branch Chief from the NRC's Region III Office. y Roy Caniano, a Paperiello, Director of the NRC's Office of Nuclear Naterial Dr. Carl i

Safety and Safeguards, and other NRc staff members will also attend the meeting.

to weld a shield lid on the spent fuel storage container after i

was loaded with 24 fuel assemblies.

There was no evidence of damage to the storage container er to the fuel assemblies as a result of the gas burn.

j The spent fuel assemblies were subsequently placed back in the spent fuel storage pool.

The investigation into the cause of the incident is focussing on a zinc-based coating used on internal surfaces of the container.

acidic water from the spent fuel storage pool to produceThe coating m hydrogen.

The meeting between the NRC staff and Wisconsin Electric officials will be open to public observation.

At the close of the meeting there will be an opportunity for questions and comments from members of the public.

  1. 9i#i

. _.

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