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* L consumers Power company Director of Nuclear Reactor  
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consumers
.. Att: Mr Albert Schwencer, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255, LICENSE DPR-20 -PALISADES PLANT -CONTAINMENT AIR LOCK TESTING On July 30, 1976 representatives of Consumers Power Company met with members of your staff to discuss our request for an exemption from the regulation in Appendix J which r*equires that air locks be tested after each opening . At the meeting, it appeared that a major staff concern related to possible advertent damage of the door sealing gaskets which could result in undetected loss.in door seal integrity for a long period of time. This damage could occur during passagt? .. of personnel and equipment through the lock. ,
* Power company Director of Nuclear Reactor Regulati~n~..~~~a_rn.,.,.,~_~.~~~~~;~:..
-(,'. The following discussion formalizes the information presented at the July 30, 1976 meeting and represents some additional consideration related to the question of door seal reliability.
Att: Mr Albert Schwencer, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255, LICENSE DPR       PALISADES PLANT - CONTAINMENT AIR LOCK TESTING On July 30, 1976 representatives of Consumers Power Company met with members of your staff to discuss our request for an exemption from the regulation in Appendix
As discussed in the July meeting, complete documentation of air lock leakage problems, which have occurred within the industry, has not been available to us and we would like to review this data as soon as your staff is able to make it available.
* J which r*equires that air locks be tested after each opening .
The Palisades Plant first went critical in April of 1971 with about five and half years of operating experience occurring since that time. A review of our maintenance and inspection records shows that no damage to the rubber seals or stainless steel sealing surfaces has occurred.
At the meeting, it appeared that a major staff concern related to possible in-advertent damage of the door sealing gaskets which could result in undetected loss.in door seal integrity for a long period of time. This damage could occur during passagt?..of personnel and equipment through the lock.
The original gaskets are still in use and performing satisfactorily.
                  , .;;:~*- -
Figure 1 is a general drawing of a personnel air lock manufactured by the W J Wooley Company. It is designed to contain a pressure of 55 psig, though it has been tested to 63 psig, and it encloses 869 ft3. In the upper right-hand corner is a detailed drawing showing the seating surfaces.
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It should be noted there are two gaskets (each of 45 dirometer.
The following discussion formalizes the information presented at the July 30, 1976 meeting and represents some additional consideration related to the question of door seal reliability. As discussed in the July meeting, complete documentation of air lock leakage problems, which have occurred within the industry, has not been available to us and we would like to review this data as soon as your staff is able to make it available.
hardness) per door, while only one gasket is needed to seal the penetration.  
The Palisades Plant first went critical in April of 1971 with about five and one-half years of operating experience occurring since that time. A review of our maintenance and inspection records shows that no damage to the rubber seals or stainless steel sealing surfaces has occurred. The original gaskets are still in use and performing satisfactorily.
*since there are two doors, four seals exist tween the containment and the outside, any one of which would provide the sary integrity.
Figure 1 is a general drawing of a personnel air lock manufactured by the W J Wooley Company. It is designed to contain a pressure of 55 psig, though it has been tested to 63 psig, and it encloses 869 ft3. In the upper right-hand corner is a detailed drawing showing the seating surfaces. It should be noted there are two gaskets (each of 45 dirometer. hardness) per door, while only one gasket is needed to seal the penetration. *since there are two doors, four seals exist be-
The rubber gaskets in their seats are below the shoulders of the gasket frame. This protection undoubtedly partially explains why none of the gaskets have been damaged.
* tween the containment and the outside, any one of which would provide the neces-sary integrity. The rubber gaskets in their seats are below the shoulders of the gasket frame. This protection undoubtedly partially explains why none of the gaskets have been damaged.
* *
 
* 2 There is a 1/8" pipe tap between the gaskets on each door so each door can be ually tested to verify both seals are holding. These were used when the doors were first installed and the one time it was necessary to adjust (shim) the ber gaskets for a tighter seal. Figure 2 is a picture of the outside of the auxiliary building door of the Palisades air lock whereas Figure 3 is a picture of the inside of the same door. The remaining pictures are close-ups of the 11 2 o'clock" and the 11 10 o'clock" regions. Figure 4 is at the "2 o'clock" location.
2
The dark area adjacent to the door is the edge of the gasket. Figure 5 is also the 11 2 o'clock" location with the door open. The rubber seals and the frame are plainly seen. Finally, Figure 6 is a picture of the "10 o'clock" location with the door open. The stainless steel lips on the doors are clearly visible as are the mating rubber gaskets. Since this air lock is part of the containment isolation system, the present Technical Specifications require that the air lock be tested at rated pressure (55 psig) every six months (provided containment isolation was necessary during that period). Though no specific maximum leakage limit exists for the personnel air lock, the plant is restricted to 60,000 cc/min total leakage for all ment penetrations.
* There is a 1/8" pipe tap between the gaskets on each door so each door can be man-ually tested to verify both seals are holding. These were used when the doors were first installed and the one time it was necessary to adjust (shim) the rub-ber gaskets for a tighter seal.
The results of the personnel air lock leakage tests are shown in Table 1. The leakage is generally less than 7% of our total allowable leakage. In one instance (August 1974), a leak in the air lock was found. This leak was corrected by placing a shim under the gasket at that location.
Figure 2 is a picture of the outside of the auxiliary building door of the Palisades air lock whereas Figure 3 is a picture of the inside of the same door.
No other changes have been necessary in over five years. The original gaskets are still in place. Since Palisades first went critical, it has been beset by an abnormal amount of equipment problems.
The remaining pictures are close-ups of the 11 2 o'clock" and the 11 10 o'clock" regions.
This has resulted in maintenance activities that are mated to be two to three times more than normal. Further, much o*f this nance involved steam generator repairs, primary access to which is via the sonnel air lock. During the last outage, approximately 80 people per day passed through this air lock. While damage to the door sealing surfaces might be contemplated as a result of this type of activity, the fact still remains that no damage has occurred to any one of the four sealing surfaces in what would be 10 to 15 years of exposure in most plants. At Palisades, the location of the air lock may have served to tect the sealing surface. Both doors to the air lock are protected, each entering essentially a protected chamber. Both are covered from above and on at least two sides so large or heavy equipment is not readily taken through the air lock. If a system were permanently installed to permit either automatic or manual ing of the door sealing surfaces (through pressurizing between the gaskets), it would not only be an added expense and additional maintenance requirement but would also raise questions relating to reducing containment integrity.
Figure 4 is at the "2 o'clock" location. The dark area adjacent to the door is the edge of the gasket. Figure 5 is also the 11 2 o'clock" location with the door open. The rubber seals and the frame are plainly seen. Finally, Figure 6 is a picture of the "10 o'clock" location with the door open. The stainless steel lips on the doors are clearly visible as are the mating rubber gaskets.
The addition of testing equipment would add possible leakage paths and dependence on the integrity of added valves and controller.
Since this air lock is part of the containment isolation system, the present Technical Specifications require that the air lock be tested at rated pressure (55 psig) every six months (provided containment isolation was necessary during that period). Though no specific maximum leakage limit exists for the personnel air lock, the plant is restricted to 60,000 cc/min total leakage for all contain-ment penetrations. The results of the personnel air lock leakage tests are shown in Table 1. The leakage is generally less than 7% of our total allowable leakage.
We conclude that this loss in rity would tend to offset any gains that might be made, This is especially true in light of the continuing good experience we have had with the sealing surfaces of the air locks,
* In one instance (August 1974), a leak in the air lock was found. This leak was corrected by placing a shim under the gasket at that location. No other changes have been necessary in over five years. The original gaskets are still in place.
* * * .e 3 A current review of our present air lock testing procedures shows that the standard full pressure test of the lock (normally made every 6 months and at 55 psig) would not necessarily assure the integrity of both sealing surfaces on each door.* To add additional assurance of the sealing surface integrity, the standard 6-month test will include a between seal leak test, or some other equivalent method, to demonstrate the integrity of both seals. In addition to the experience observed at our Palisades Plant we have also viewed our maintenance records for our Big Rock Point facility.
Since Palisades first went critical, it has been beset by an abnormal amount of equipment problems. This has resulted in maintenance activities that are esti-mated to be two to three times more than normal. Further, much o*f this mainte-nance involved steam generator repairs, primary access to which is via the per-sonnel air lock. During the last outage, approximately 80 people per day passed through this air lock.
This review covers records from 1963 to the present time. Big Rock Point has three air locks which utilize single gaskets on each door. These gaskets and the sealing surface are arranged very similar to that discussed for our Palisades Plant. Two of the air locks are used extensively for passage of personnel and equipment.
While damage to the door sealing surfaces might be contemplated as a result of this type of activity, the fact still remains that no damage has occurred to any one of the four sealing surfaces in what would be 10 to 15 years of exposure in most plants. At Palisades, the location of the air lock may have served to pro-tect the sealing surface. Both doors to the air lock are protected, each entering essentially ~nto a protected chamber. Both are covered from above and on at least two sides so large or heavy equipment is not readily taken through the air lock.
The personnel lock is operated 24 times per day for operator surveillance alone with many additional operations occurring to permit maintenance activities, etc. The results of the Big Rock Point personnel and equipment air lock leakage tests are shown in Table 2. Both of these locks experience considerable use. The equipment lock is generally used to pass both small and large pieces of ment including items such as fuel shipping casks. This lock is accessed by overhead on both sides (with a track and dolly providing passage through the lock). No mechanical type damage to either of the sealing surfaces is known to have occurred since operation began in 1962. The records disclosed that corrective maintenance involving the door seal has(b}en required on only a few occasions.
If a system were permanently installed to permit either automatic or manual test-ing of the door sealing surfaces (through pressurizing between the gaskets), it would not only be an added expense and additional maintenance requirement but would also raise questions relating to reducing containment integrity. The addition of testing equipment would add possible leakage paths and dependence on the integrity of added valves and controller. We conclude that this loss in integ-rity would tend to offset any gains that might be made, This is especially true
These activities.
* in light of the continuing good experience we have had with the sealing surfaces of the air locks,
were performed to prevent 1 leakage from becoming acceptably high and none were the result of* gasket damage. We conclude that the operating experience at our Big Rock facility gives further support and justification to our request for an exemption from testing of air locks (within 72 hours of use). (l)Plant records for October of 1963 show an apparently unacceptable leakage rate for the escape lock. The cause of this leakage is not known but since the lock is seldom used and we have no record of gasket replacement, it is considered unlikely that it was related to gasket damage . The maintenance records were also unable to account for one personnel lock gasket. While we cannot determine the reasons for the use of this gasket, cussion with various staff members disclosed no gasket problems that were lated to inadvertent gasket damage.
 
* *
3
* 4 .e This information has been provided for your consideration regarding our exemption request. We are confident that sufficient basis exists to demonstrate that this exemption will not endanger life or property and is in the public interest.
                            .e
David A. Bixel Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC
* A current review of our present air lock testing procedures shows that the standard full pressure test of the lock (normally made every 6 months and at 55 psig) would not necessarily assure the integrity of both sealing surfaces on each door.* To add additional assurance of the sealing surface integrity, the standard 6-month test will include a between seal leak test, or some other equivalent method, to demonstrate the integrity of both seals.
* * * .e TABLE 1 Palisades Nuclear Plant The following is a list of the results of all known Local Leak Tests conducted by Consumers Power Company on the Palisades Plant personnel air lock, The Specifications limit for all penetrations is approximately 60,000 cc/min. Testing Period Date Leakage Results (cc/Min) March 197i 1085 October -November 1971 5171 April -May 1972 3243 October -November 1972 4190 January -March 1973 3037 April -June 1973 4030 November 1973 -April 1974 4520.0 December 1974 -January 1975 6076.9 July -August 1975 2631.4 January -April 1976 4021.0 In August of 1974 a Leak Test was performed between the seals on the air lock inner door* This test was performed to identify a postulated seal leakage on the inner door. A was identified, the seal shimmed, and an after maintenance leakage of 62,7 cc/min resulted from the "between the seal" test *
In addition to the experience observed at our Palisades Plant we have also re-viewed our maintenance records for our Big Rock Point facility. This review covers records from 1963 to the present time.
* * * .e TABLE 2 Big Rock Point Nuclear Plant Leakage Rates in Pounds/24 Hours The Technical Specifications limit for all penetrations is approximately 410 pounds/24 hours. . Date 4/ 4/63 9/22/63 10/10/63 2/12/64 2/22/64 8/20/64 8/21/64 2/ 9/65 8/24/65 2/ 5/66 8/13/66 2/21/67 . 8/18/67 3/ 4/68 9/ 9/68 4/ 2/69 10/14/69 4/14/70 10/11/70 4/14/71 10/11/71 3/ 7 /72 11/ 6/72 4/25/73 10/ 8/73 3/22/74 9/30/74 3/2,2/75 3/27/75 4/27/75 9/22/75 4/21/76 Equipment Lock 11. 7. 32.404 0 23,608 31.764 24.62 16,58 12,80 87.467 0.0 16,o 48,55 0.0 0.0 0.0 32.30 61.6 1.44 70.865 121.29 133.11 42.52 26,40 32.9 27.66 18,84 13.9 31,74 8.69 8,74 20.55 12.63 Personnel Lock 261 52.56 11.632 25.091 3.895 10.342 10.14 23.78 0.7997 2.3 1.34 17.55 7.9 0.0 34.2 7.73 6.75 6.08 1.44 6.95 0.0 3.38 4.95 8.5 4.83 4.84 6.7 52.07 17.42 17.42 4.9 1. 7 C"""R * *  
Big Rock Point has three air locks which utilize single gaskets on each door.
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These gaskets and the sealing surface are arranged very similar to that discussed for our Palisades Plant. Two of the air locks are used extensively for passage of personnel and equipment. The personnel lock is operated 24 times per day for operator surveillance alone with many additional operations occurring to permit maintenance activities, etc.
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The results of the Big Rock Point personnel and equipment air lock leakage tests are shown in Table 2. Both of these locks experience considerable use. The equipment lock is generally used to pass both small and large pieces of equip-ment including items such as fuel shipping casks. This lock is accessed by overhead ~ranes on both sides (with a track and dolly providing passage through
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* the lock). No mechanical type damage to either of the sealing surfaces is known to have occurred since operation began in 1962.
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The records disclosed that corrective maintenance involving the door seal has(b}en required on only a few occasions. These activities. were performed to prevent 1 leakage from becoming acceptably high and none were the result of* gasket damage.
__
We conclude that the operating experience at our Big Rock facility gives further support and justification to our request for an exemption from testing of air locks (within 72 hours of use).
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(l)Plant records for October of 1963 show an apparently unacceptable leakage rate for the escape lock. The cause of this leakage is not known but since the lock is seldom used and we have no record of gasket replacement, it is considered unlikely that it was related to gasket damage .
&,.
* The maintenance records were also unable to account for one personnel lock gasket. While we cannot determine the reasons for the use of this gasket, dis-cussion with various staff members disclosed no gasket problems that were re-lated to inadvertent gasket damage.
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* This information has been provided for your consideration regarding our exemption request. We are confident that sufficient basis exists to demonstrate that this exemption will not endanger life or property and is in the public interest.
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David A. Bixel Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC
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* TABLE 1 Palisades Nuclear Plant The following is a list of the results of all known Local Leak Tests conducted by Consumers Power Company on the Palisades Plant personnel air lock, The Technic~l Specifications limit for all penetrations is approximately 60,000 cc/min.
* G I , 1t.
Testing Period Date               Leakage Results (cc/Min)
* l { ( l .e FIGURE 2 FIGURE 3 * 
March 197i                                     1085 October - November 1971                         5171 April - May 1972                               3243 October - November 1972                         4190 January - March 1973                           3037 April - June 1973                               4030
.e FIGURE 4
* November 1973 - April 1974 December 1974 - January 1975 July - August 1975 4520.0 6076.9 2631.4 January - April 1976                           4021.0 In August of 1974 a Leak Test was performed between the seals on the air lock inner door* This test was performed to identify a postulated seal leakage on the inner door. A ~eak was identified, the seal shimmed, and an after maintenance leakage of 62,7 cc/min resulted from the "between the seal" test *
* RUBBER GASKET . *
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* TABLE 2 Big Rock Point Nuclear Plant Leakage Rates in Pounds/24 Hours The Technical Specifications limit for all penetrations is approximately 410 pounds/24 hours.                   .
* STL. SEALING LIP GASKETS * *}}
Date             Equipment Lock            Personnel Lock 4/ 4/63               11. 7.                    261 9/22/63               32.404                    52.56 10/10/63               0                        11.632 2/12/64               23,608                    25.091 2/22/64               31.764                    3.895 8/20/64               24.62                    10.342 8/21/64               16,58                    10.14 2/ 9/65               12,80                    23.78 8/24/65               87.467                    0.7997 2/ 5/66               0.0                      2.3 8/13/66               16,o                      1.34 2/21/67               48,55                    17.55
*
          . 8/18/67               0.0                      7.9 3/ 4/68               0.0                      0.0 9/ 9/68               0.0                      34.2 4/ 2/69               32.30                    7.73 10/14/69               61.6                      6.75 4/14/70               1.44                      6.08 10/11/70               70.865                    1.44 4/14/71               121.29                    6.95 10/11/71               133.11                    0.0 3/ 7 /72               42.52                    3.38 11/ 6/72               26,40                    4.95 4/25/73               32.9                      8.5 10/ 8/73               27.66                    4.83 3/22/74               18,84                    4.84 9/30/74               13.9                      6.7 3/2,2/75               31,74                    52.07 3/27/75               8.69                      17.42 4/27/75               8,74                      17.42 9/22/75               20.55                    4.9 4/21/76               12.63                    1. 7
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Revision as of 09:11, 20 October 2019

Referring to Meeting of 7/30/1976 Regarding Appendix J Which Requires Air Locks Be Tested After Each Opening, Letter Providing Information for NRC Consideration to CPC Exemption Request
ML18347A558
Person / Time
Site: Palisades Entergy icon.png
Issue date: 09/27/1976
From: Bixel D
Consumers Power Co
To: Schwencer A
Office of Nuclear Reactor Regulation
References
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  • Power company Director of Nuclear Reactor Regulati~n~..~~~a_rn.,.,.,~_~.~~~~~;~:..

Att: Mr Albert Schwencer, Chief Operating Reactor Branch No 1 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255, LICENSE DPR PALISADES PLANT - CONTAINMENT AIR LOCK TESTING On July 30, 1976 representatives of Consumers Power Company met with members of your staff to discuss our request for an exemption from the regulation in Appendix

  • J which r*equires that air locks be tested after each opening .

At the meeting, it appeared that a major staff concern related to possible in-advertent damage of the door sealing gaskets which could result in undetected loss.in door seal integrity for a long period of time. This damage could occur during passagt?..of personnel and equipment through the lock.

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The following discussion formalizes the information presented at the July 30, 1976 meeting and represents some additional consideration related to the question of door seal reliability. As discussed in the July meeting, complete documentation of air lock leakage problems, which have occurred within the industry, has not been available to us and we would like to review this data as soon as your staff is able to make it available.

The Palisades Plant first went critical in April of 1971 with about five and one-half years of operating experience occurring since that time. A review of our maintenance and inspection records shows that no damage to the rubber seals or stainless steel sealing surfaces has occurred. The original gaskets are still in use and performing satisfactorily.

Figure 1 is a general drawing of a personnel air lock manufactured by the W J Wooley Company. It is designed to contain a pressure of 55 psig, though it has been tested to 63 psig, and it encloses 869 ft3. In the upper right-hand corner is a detailed drawing showing the seating surfaces. It should be noted there are two gaskets (each of 45 dirometer. hardness) per door, while only one gasket is needed to seal the penetration. *since there are two doors, four seals exist be-

  • tween the containment and the outside, any one of which would provide the neces-sary integrity. The rubber gaskets in their seats are below the shoulders of the gasket frame. This protection undoubtedly partially explains why none of the gaskets have been damaged.

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  • There is a 1/8" pipe tap between the gaskets on each door so each door can be man-ually tested to verify both seals are holding. These were used when the doors were first installed and the one time it was necessary to adjust (shim) the rub-ber gaskets for a tighter seal.

Figure 2 is a picture of the outside of the auxiliary building door of the Palisades air lock whereas Figure 3 is a picture of the inside of the same door.

The remaining pictures are close-ups of the 11 2 o'clock" and the 11 10 o'clock" regions.

Figure 4 is at the "2 o'clock" location. The dark area adjacent to the door is the edge of the gasket. Figure 5 is also the 11 2 o'clock" location with the door open. The rubber seals and the frame are plainly seen. Finally, Figure 6 is a picture of the "10 o'clock" location with the door open. The stainless steel lips on the doors are clearly visible as are the mating rubber gaskets.

Since this air lock is part of the containment isolation system, the present Technical Specifications require that the air lock be tested at rated pressure (55 psig) every six months (provided containment isolation was necessary during that period). Though no specific maximum leakage limit exists for the personnel air lock, the plant is restricted to 60,000 cc/min total leakage for all contain-ment penetrations. The results of the personnel air lock leakage tests are shown in Table 1. The leakage is generally less than 7% of our total allowable leakage.

  • In one instance (August 1974), a leak in the air lock was found. This leak was corrected by placing a shim under the gasket at that location. No other changes have been necessary in over five years. The original gaskets are still in place.

Since Palisades first went critical, it has been beset by an abnormal amount of equipment problems. This has resulted in maintenance activities that are esti-mated to be two to three times more than normal. Further, much o*f this mainte-nance involved steam generator repairs, primary access to which is via the per-sonnel air lock. During the last outage, approximately 80 people per day passed through this air lock.

While damage to the door sealing surfaces might be contemplated as a result of this type of activity, the fact still remains that no damage has occurred to any one of the four sealing surfaces in what would be 10 to 15 years of exposure in most plants. At Palisades, the location of the air lock may have served to pro-tect the sealing surface. Both doors to the air lock are protected, each entering essentially ~nto a protected chamber. Both are covered from above and on at least two sides so large or heavy equipment is not readily taken through the air lock.

If a system were permanently installed to permit either automatic or manual test-ing of the door sealing surfaces (through pressurizing between the gaskets), it would not only be an added expense and additional maintenance requirement but would also raise questions relating to reducing containment integrity. The addition of testing equipment would add possible leakage paths and dependence on the integrity of added valves and controller. We conclude that this loss in integ-rity would tend to offset any gains that might be made, This is especially true

  • in light of the continuing good experience we have had with the sealing surfaces of the air locks,

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  • A current review of our present air lock testing procedures shows that the standard full pressure test of the lock (normally made every 6 months and at 55 psig) would not necessarily assure the integrity of both sealing surfaces on each door.* To add additional assurance of the sealing surface integrity, the standard 6-month test will include a between seal leak test, or some other equivalent method, to demonstrate the integrity of both seals.

In addition to the experience observed at our Palisades Plant we have also re-viewed our maintenance records for our Big Rock Point facility. This review covers records from 1963 to the present time.

Big Rock Point has three air locks which utilize single gaskets on each door.

These gaskets and the sealing surface are arranged very similar to that discussed for our Palisades Plant. Two of the air locks are used extensively for passage of personnel and equipment. The personnel lock is operated 24 times per day for operator surveillance alone with many additional operations occurring to permit maintenance activities, etc.

The results of the Big Rock Point personnel and equipment air lock leakage tests are shown in Table 2. Both of these locks experience considerable use. The equipment lock is generally used to pass both small and large pieces of equip-ment including items such as fuel shipping casks. This lock is accessed by overhead ~ranes on both sides (with a track and dolly providing passage through

  • the lock). No mechanical type damage to either of the sealing surfaces is known to have occurred since operation began in 1962.

The records disclosed that corrective maintenance involving the door seal has(b}en required on only a few occasions. These activities. were performed to prevent 1 leakage from becoming acceptably high and none were the result of* gasket damage.

We conclude that the operating experience at our Big Rock facility gives further support and justification to our request for an exemption from testing of air locks (within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of use).

(l)Plant records for October of 1963 show an apparently unacceptable leakage rate for the escape lock. The cause of this leakage is not known but since the lock is seldom used and we have no record of gasket replacement, it is considered unlikely that it was related to gasket damage .

  • The maintenance records were also unable to account for one personnel lock gasket. While we cannot determine the reasons for the use of this gasket, dis-cussion with various staff members disclosed no gasket problems that were re-lated to inadvertent gasket damage.

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  • This information has been provided for your consideration regarding our exemption request. We are confident that sufficient basis exists to demonstrate that this exemption will not endanger life or property and is in the public interest.

David A. Bixel Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC

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  • TABLE 1 Palisades Nuclear Plant The following is a list of the results of all known Local Leak Tests conducted by Consumers Power Company on the Palisades Plant personnel air lock, The Technic~l Specifications limit for all penetrations is approximately 60,000 cc/min.

Testing Period Date Leakage Results (cc/Min)

March 197i 1085 October - November 1971 5171 April - May 1972 3243 October - November 1972 4190 January - March 1973 3037 April - June 1973 4030

  • November 1973 - April 1974 December 1974 - January 1975 July - August 1975 4520.0 6076.9 2631.4 January - April 1976 4021.0 In August of 1974 a Leak Test was performed between the seals on the air lock inner door* This test was performed to identify a postulated seal leakage on the inner door. A ~eak was identified, the seal shimmed, and an after maintenance leakage of 62,7 cc/min resulted from the "between the seal" test *

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  • TABLE 2 Big Rock Point Nuclear Plant Leakage Rates in Pounds/24 Hours The Technical Specifications limit for all penetrations is approximately 410 pounds/24 hours. .

Date Equipment Lock Personnel Lock 4/ 4/63 11. 7. 261 9/22/63 32.404 52.56 10/10/63 0 11.632 2/12/64 23,608 25.091 2/22/64 31.764 3.895 8/20/64 24.62 10.342 8/21/64 16,58 10.14 2/ 9/65 12,80 23.78 8/24/65 87.467 0.7997 2/ 5/66 0.0 2.3 8/13/66 16,o 1.34 2/21/67 48,55 17.55

. 8/18/67 0.0 7.9 3/ 4/68 0.0 0.0 9/ 9/68 0.0 34.2 4/ 2/69 32.30 7.73 10/14/69 61.6 6.75 4/14/70 1.44 6.08 10/11/70 70.865 1.44 4/14/71 121.29 6.95 10/11/71 133.11 0.0 3/ 7 /72 42.52 3.38 11/ 6/72 26,40 4.95 4/25/73 32.9 8.5 10/ 8/73 27.66 4.83 3/22/74 18,84 4.84 9/30/74 13.9 6.7 3/2,2/75 31,74 52.07 3/27/75 8.69 17.42 4/27/75 8,74 17.42 9/22/75 20.55 4.9 4/21/76 12.63 1. 7

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