RS-06-099, Response to Request for Additional Information Re Request for Relief from the ASME OM Code for the Third Inservice Test Interval
| ML061930087 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/11/2006 |
| From: | Bauer J Exelon Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-06-099 | |
| Download: ML061930087 (9) | |
Text
RS-06-099 July 11, 2006 U. S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, D. C. 20555 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. 50-454 and 50-455 10 CFR 50.55a Subject :
Response to Request for Additional Information Related to Request for Relief from the ASME OM Code for the Third Inservice Test Interval References :
(1)
Letter from D. M. Hoots (Exelon Generation Company, LLC) to USNRC, "Byron Station, Units 1 and 2, Requests for Relief from the ASME OM Code for the Third Inservice Test Interval," dated December 29, 2005 (2)
USNRC to C. M. Crane (Exelon Generation Company, LLC), "Byron Station, Unit Nos. 1 and 2 - Request for Additional Information Related to Request for Relief from the ASME OM Code for the Third Inservice Test Interval," dated June 13, 2006 In Reference 1, Exelon Generation Company, LLC, (EGC), requested approval of proposed alternatives to the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, 2001 Edition through 2003 Addenda, for Byron Station, Units 1 and 2. These proposed alternatives are for the Byron Station Third Inservice Testing (IST) interval, which began on July 1, 2006 and will end on June 30, 2016. Specifically, the proposal requested seven relief requests.
In Reference 2, the NRC requested additional information to complete the review of the proposed relief request. Attachment 1 of this letter provides the requested information.
After technical discussions with the NRC, EGC has elected to withdraw two relief requests proposed in Reference 1 ; RP-4, "Auxiliary Feedwater Essential Service Water Booster Pump Comprehensive Test" and RP-6, "Comprehensive Pump Test Alert Range Frequency."
July 11, 2006 U. S. Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Mr. John Schrage at (630) 65T2821.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 11 to day of July 2006.
Respectfully, Joseph A. Bauer Manager, Licensing : Response to Request for Additional Information Enclosure A : Component Cooling Water Pump Comprehensive Test Data Enclosure B : Control Room Chilled Water Pump Comprehensive Test Data
Question No. 1 Relief request RP-2 (Category 1.10)
Provide pump data that compares pump performance to the acceptance criteria identified in Table ISTBO100-1 for the Comprehensive Pump Test for each of the last three cycles.
Response
Comprehensive Pump Test data for the Component Cooling Water pumps is provided in Enclosure A.
Question No. 2 Relief request RP-3 (Category 1.b)
Provide pump data that compares pump performance to the acceptance criteria identified in Table ISTB-51 00-1 for the Comprehensive Pump Test for each of the last three cycles.
Response
Comprehensive Pump Test data for the Control Room Chilled Water pumps is provided in Enclosure B.
Question No. 3 Relief request RP-4 (Category 1.b)
ATTACHMENT I Response to Request for Additional Information Provide pump data that compares pump performance to the acceptance criteria identified in Table ISTB01 00-1 for the Comprehensive Pump Test for each of the last three cycles.
Response
After technical discussions with the NRC, Exelon Generation Company, LLC (EGC) has elected to withdraw Relief Request RP-4, "Auxiliary Feedwater Essential Service Water Booster Pump Comprehensive Test," which was originally submitted in Reference 1.
Question No. 4 Relief request RP-6 (Category 1.b)
Provide discussion on how this relief request provides an acceptable level of quality. The discussion provided describes the proposed alternative, but does not describe how it provides an acceptable level of quality.
Response
After technical discussions with the NRC, EGC has elected to withdraw Relief Request RP-6, "Comprehensive Pump Test Alert Range Frequency," which was originally submitted in Reference 1.
Question No. 5 Relief request RV-1 (Category 2.a)
ATTACHMENT 1 Response to Request for Additional Information This Relief Request proposes an alternative that would provide an acceptable level of quality and safety for the exercising test frequency of four valves. The discussion provided describes the impracticality of the actions necessary to stroke these valves. Provide a discussion as to how the change of stroking the valves quarterly to stroking them once every 18 months with a 25 percent allowance for flexibility in scheduling provides a similar level of quality and safety.
Include information regarding the environmental and chemical effects on the ability to stroke the valves.
Response
The containment recirculation sump isolation valves at Byron Station (i.e., 1(2) 518811 A/B valves) provide an isolation boundary between the suctions of the Residual Heat Removal (RH) and Containment Spray (CS) pumps, and the containment recirculation sumps. A stroke test of these valves requires that the RH and CS pumps, for a given train, be removed from service, and the suction lines drained to prevent water flow from the Refueling Water Storage Tank (RWST) and associated piping into the normally empty containment recirculation sump.
This evolution (i.e., drain, test, refill, and restore the system configuration to normal status) requires approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to complete. In addition, the testing process will render a train of RH and CS inoperable for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> each quarter. Based upon the complexity of the actions that are required to stroke test the valves, as well as the impact upon plant configuration and risk associated with the concurrent inoperability of an RH and CS train, it is not practicable to perform these activities on a quarterly frequency.
American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants, 2001 Edition through 2003 Addenda (i.e., ASME OM Code), Section ISTC-3521, "Category A and Category B Valves," paragraph (e) states : " if exercising is not practicable at power or cold shutdowns, it may be limited to full-stroke during refueling outages." The impractical nature of testing these valves during operation provides justification to implement an extended test frequency of once per refueling outage.
The history of both maintenance and In-Service Testing (IST) for all eight of the containment recirculation sump valves at Braidwood Station and Byron Station indicates good materiel condition and acceptable test results (i.e., stroke times). This testing history also demonstrates an acceptable level of quality and safety for an extended test frequency of once per refueling outage, relative to the quarterly frequency.
Based upon the guidance provided in the ASME OM Code, Section ISTC-3521, and the duration of a normal refueling cycle at Byron Station, EGC has requested an alternate test frequency of once per refueling cycle for the containment recirculation sump isolation valves (i.e., once every 18 months with a 25% allowance, as opposed to once per refueling outage).
Since Byron Station operates on an 18-month fuel cycle, the refueling outages are approximately 18 months apart. An 18-month frequency, with a 25% allowance for scheduling Page 2 of 3
ATTACHMENT 1 Response to Request for Additional Information flexibility, as described in the Relief Request, provides the same level of quality and safety as once per refueling outage. In addition, the 18-month frequency, with a 25% allowance, will enable Byron Station to optimize the availability of the RH and CS systems by scheduling the stroke tests concurrent with other plant activities.
With respect to specific information regarding the environmental and chemical effects on the ability to stroke the valves, after additional discussion, the NRC indicated that this information was no longer required.
References :
1. Letter from D. M. Hoots (Exelon Generation Company, LLC) to USNRC, "Byron Station, Units 1 and 2, Requests for Relief from the ASME OM Code for the Third Inservice Test Interval," dated December 29, 2005
- 2. USNRC to C. M. Crane (Exelon Generation Company, LLC), "Byron Station, Unit Nos. 1 and 2 - Request for Additional Information related to Request for Relief from the ASME OM Code for the Third Inservice Test Interval," dated June 13, 2006
Enclosure A Component Cooling Water Pump Comprehensive Test Data OCCO1 P Test Data Current Reference Value = 105 1 0001 PA Test Data Current Reference Value = 103.5 Page 1 of 3 Test Date Flow Rate (set)
Differential Pressure Acceptable Range
-.Alert Range Required Action Range -
Low Required Action Range -
High 21-Feb-06 5115.0 103.5 96.3-106.6 93.2 to < 913
< 93.2
> 106.6 22-Nov-05 5154.4 99.5 96.3-106.6 93.2 to < 96.3
< 912
> 10&6 23-Aug-05 5146.0 102.5 9&3 - 1016 93.2 to < 9&3
< 93.2
> 10&6 23-Ma -05 0270 1005 9&3 - 10&6 932 to < 9&3
< 93.2
> 1046 22-Feb-05 5178.0 104.0 96.3-106.6 93.2 to < 96.3
< 93.2
> 106.6 23-Nov-04 5138.0 103.0 96.3 - 10&6 93.2 to < 96.3
< 93.2
> 106.6 24-Aug-04 5110.0 100.5 96.3-106.6 93.2 to < 913
< 932
> 106.6 27-May-04 5280.0 99.0 96.3 - 10&6 93.2 to < 96.3
< 93.2
> 106.6 23-Feb-04 5280.0 99.0 96.3-106.6 93.2 to < 96.3
< 93.2
> 106.6 24-Nov-03 5224.0 99.0 9&3 - 10&6 93.2 to < 96.3
< 93.2
> 106.6 26-Aug-03 5187.0 99.0 96.3-106.6 93.2 to < 96.3
< 93.2
> 106.6 27-May-03 5217.0 99.0 96.3 - 10&6 93.2 to < 96.3
< 93.2
> 106.6 24-Feb-03 5197.0 100.0 96.3-1056 932 to < 96.3
< 93.2
> 10&6 17-Dec-02 5220.0 101.0 96.3-106.6 93.2 to < 96.3
< 93.2
> 106.6 27-AuqT2 5129.0 102.0 963 - 10&6 932 to < 96.3
< 93.2
> 10&6 09-Oct-01 5132.0 100.5 96.3-106.6 93.2 to < 9&3
< 93.2
> 10&6 02-A r-01 5262.0 97.0 963 - 10&6 932 to < 96.3
< 93.2 106.6 08-Jan-01 1 5230.0 99.5 1
96.3 110&6 1932 to < 96.3
< 93.2
> 10&6 Test Date Flow Rate (set)
Differential Pressure Acceptable Range Alert Range Required Action Range -
Low Required Action Range -
-IHi h 18-A r-06 5084.0 106.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 17-Jan-06 5125.0 104.5 97.7 - 108.2 94.5 to < 97.7
< 94.5
> 108.2 18-Oct-05 51 "621 106.0 97.7 - 108.2 94.5 to < 97.7
< 915
> 108.2 19-Jut-05 51021 107.5 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 18-A r-05 51481 10&5 971 - 108.2 941 to < 97. 7
< 915
> 108.2 18-Jan-05 5204.0 106.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 18-Oct-04 5216.0 106.0 97.7 - 108.2 915 to < 97.7
< 915
> 108.2 20-Jut-04 51131 105.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 20-A r-04 5193.0 104.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 20-Jan-04 5115.0 104.5 97.7 - 108.2 94.5 to < 97.7
< 915
> 108.2 04-Dec-03 5120.0 103.0 971 - 108.2 94.5 to < 97.7
< 915
> 108.2 21-Oct-03 5208.0 102.0 97.7 - 108.2 915 to < 97.7
< 915
> 108.2 22-Jul-03 5201.0 103.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 21-A pr-03 5210.0 103.0 97.7 - 108.2 945 to < 97.7
< 915
> 108.2 21-Jan-03 5179.0 104.0 97.7 - 108.2 94.5 to < 97.7
< 915
> 108.2 21-Oct-02 5074.0 101.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 07-May-01 5210.0 102.0 97.7 - 108.2 915 to < 97.7
< 915
> 108.2
Enclosure A Component Cooling Water Pump Comprehensive Test Data 1 0001 PB Test Data Current Reference Value =101 20001 PA Test Data Current Reference Value =103 Page 2 of 3 Test Date Flow Rate (set)
Differential Pressure Acceptable Range Alert Ranqe Required Action Range -
Low Required Action Range -
High 25-A r-06 52001 1020 95.8-106.1 92.7 to < 95.8
< 92.7
> 106.1 23-Jan-06 5150.0 103.0 95.8-106.1 92.7 to < 95.8
< 92.7
> 106.1 24-Oct-05 5330.0 100.5 953 - 106.1 92.7 to < 95.8
< 92.7
> 106.1 25-Jut-05 5182.0 103.0 95.8-1011 92.7 to < 95.8
< 921
> 1106.1 26-A r-05 5318.0 101.5 918-106.1 92.7 to < 95.8
< 92.7
> 106.1 28-Jan-05 5153.0 104.0 95.8-106.1 92.7 to < 95.8
< 92.7
> 106.1 27-Jul-04 5150.0 102.0 95.8-106.1 92.7 to < 95.8
< 92.7
> 106.1 28-A r-04 5227.0 99.0 95.8-106.1 92.7 to < 95.8
< 92.7
> 106.1 27-Jan-04 5256.0 100.0 95.8-106.1 92.7 to < 95.8
< 92.7
> 106.1 28-Oct-03 5215.0 98.0 95.8-106.1 92.7 to < 95.8
< 92.7
> 106.1 29-Jul-03 5238.0 101.0 95.8-106.1 92.7 to < 918
< 92.7
> 106.1 29-A r-03 5276.0 97.0 95.8-106.1 92.7 to < 95.8
< 92.7
> 1001 254a,03 52524 101.0 95.8-106.1 92.7 to < 95.8
< 921
> 106. 1 29-Oct-02 5182.0 97.5 951 - 106.1 92.7 to < 95.8
< 92.7
> 106. 1 30-J W02 52900 980 951 - 106.1 92.7 to < 95.8
< 92.7
> 106.1 31-May-01 1 5155.0 1
100.0 1
95.8-106.1 192.7 to < 95.8
< 92.7
> 106.1 Test Date Flow Rate (set)
Differential Pressure Acceptable Range Alert Range Required Action Range -
Low Required Action Range -
High 06-Mar-06 5170.0 101.0 93.9-1010 919 to < 93.9
< 90.9
> 104.0 COMM 5184.0 105.0 93.9-104.0 90.9 to < 93.9
< 90.9
> 104.0 06-SepQ5 5203.0 103.0 93.9-104.0 90.9 to < 93.9
< 90.9
> 104.0 06-Jun-05 5208.0 105.0 93.9-104.0 90.9 to < 93.9
< 90.9
> 104.0 11-Feb-05 5303.0 104.0 93.9-1010 900 to < 919 < 909 0-1010 07-Dec-04 51701 1015 919-104.0 90.9 to < 93.9
< 909
> 1000 08-Se -04 51804 1031 919-104.0 90.9 to < 93.9
< 90.9
> 104.0 08-Jun-04 5285.0 102.0 93.9-1010 90.9 to < 919
< 90.9
> 104.0 08-Mar-04 5292.0 101.5 93.9-104.0 90.9 to < 93.9
< 90.9
> 1010 09-Dec-03 5258.0 97.0 93.9-1010 90.9 to < 919 < 90.9
> 104.0 09-Se -03 47300 1000 919-1010 90.9 to < 919 < 90,
> 104. 0 09-Jun-03 5192.0 100.5 93.9-104.0 90.9 to < 93.9
< 90.9
> 104.0 11-Mar-03 5290.0 100.0 93.9-1010 90.9 to < 919
< 900
> 1010 12-Dec-02 48061 1 01.0 919-1010 90.9 to < 919
< 90.9
> 104.0 09-Se -02 5256.0 101.0 93.9-104.0 90.9 to < 919
< 90.9
> 1010 11-J ul-01 4370.0 102.0 919-1010 90.9 to < 919, 90.9
> 1010 09-May-01 4520.0 102.5 919-1010 901 to 9
> 1010 22-Jan-01 4250.0 100
.5 919. +/-10 90.9 to < g3.9l
< g0.g
> 1010
Enclosure A Component Cooling Water Pump Comprehensive Test Data 20001 PB Test Data (Current Reference Value = 105 Test Date Flow Rate (set)
Differential Pressure Acceptable Range Alert Range Required Action Range-Low Required Action Range-Hiqh 10-A pr-06 5133.0 103.5 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 12-Jan-06 5120.0 103.0 971 - 10&2 94.5 to < 97.7
< 94.5
> 108.2 01-Nov-05 5136.0 107.0 971 - 10&2 94.5 to < 97.7
< 945
> 108.2 12-Jut-05 50995 105.5 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 12-A r-05 5114.0 105.0 97.7 - 10&2 915 to < 97.7
< 915
> 10&2 11 OanT5 509.0 106.0 971 - 10&2 940 to < 97.7
< 94.5
> 108.2 12-Oct-04 5072.0 108.0 97.7 - 10&2 915 to < 97.7
< 94.5
> 108.2 1 YJW04 5170.0 102.5 97.7 - 10&2 94.5 to < 97.7
< 915
> 108.2 16-A r-04 5210.0 100.5 97.7 - 10&2 915 to < 971 < 915
> 10&2 130a,04 9081 101.0 97.7 - 10&2 915 to < 971 < 915
> 10&2 14-0503 52121 101.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 14-Jul-03 5196.0 101.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 108.2 15-A r-03 5220.0 100.0 971 - 10&2 915 to < 97.7
< 94.5
> 108.2 09-Jan-03 4612.0 101.5 971 - 10&2 94.5 to < 97.7
< 915
> 10&2 14-Oct-02 4562.0 101.0 97.7 - 10&2 915 to < 97.7
< 915
> 10&2 14-May-01 5100.0 102.0 97.7-108.2 94.5 to < 97.7
< 94.5
> 10&2
,20-Feb-01 1 4180.0 99.5 1
97.7-108.2 1 94.5 to < 97.71 < 94.5
> 108.2
Enclosure B Control Room Chilled Water Pump Comprehensive Test Data OW001 PA Test Data Current Reference Value = 63 OW001 PB Test Data Current Reference Value = 62 Test Date Flow Rate (set)
Differential Pressure Acceptable Range Alert Range Required Action Range -
Low Required Action Range -
High 02-Ma -06 56T0 610 5T7 - 619 551 to < 5T7
< 553
> 63.9 02-Feb-06 5701 610 57.7 - 609 551 to < 571
< 558
> 619 01-Nov-05 570.0 65.0 57.7-63.9 55.8 to < 57.7
< 551
> 619 140005 565.0 64.0 57.7-63.9 55.8 to < 5T7
< 518
> 619 14-A r-05 565.0 63.0 57.7-63.9 55.8 to < 5T7
< 551
> 619 10-Jan-05 5651 610 5T7 - 63.9 55.8 to < 5T7
< 518
> 619 12-0004 565.0 63.5 57.7-63.9 55.8 to < 5T7
< 55.8
> 619 1140ul-04 5721 64.0 57.7 - 619 551 to < 5T7
< 518
> 63.9 13-A r-04 570.0 63.0 57.7-63.9 55.8 to < 571
< 551
> 619 03-Jan-04 5610 610 5T7 - 63.9 55.8 to < 57.7
< 518
> 63.9 06-Now03 567.0 64.0 57.7-63.9 55.8 to < 57.7
< 518
> 619 16-Jul-03 567.0 64.0 57.7-63.9 55.8 to < 57.7
< 518
> 63.9 14-A r-03 565.0 63.0 57.7-63.9 551 to < 5T7
< 548
> 619 130a,03 5651 610 57.7-619 55.8 to < 57.7
< 551
> 619 07-May-01 572.5 62.0 57.7-63.9 55.8 to < 5T7
< 518
> 619 23-Jan-01,
568.0 63.0 57.7-63.9 55.8 to < 5T71 < 55I I
> 63.9 Test Date Flow Rate (set)
Differential Pressure Acceptable Range Alert Ranqe Required Action Range -
Low Required Action Range -
High 28-A r-06 1 570.0 1
63.0 58.6 - 619 56.7 to < 58.6 561
> 619 25-Jan-06 1 5710 -.
63.0 58.6 - 619 56.7 to < 58.6
< 56.7
> 64.9 26-Oct-05 62.0 581 - 6?9 M to < 58.6
< 547
> 6?9 27-Jut-05 051 M
5&6 - 619 563 to < 5&6
< 5&7
> 619 25-A r-05 572.0 62.0 58.6-64.9 56.7 to < 581
< 56.7
> 619 28-Jan-05 574.0 62.0 58.6-64.9 56.7 to < 58.6
< 561
> 619 28-Oct-04 578.0 61.5 58.6-64.9 56.7 to < 58.6
< 56.7
> 619 29-Jut-04 575.0 61.0 58.6 - 64.9 561 to < 58.6
< 56.7
> 619 27-A r-04 572.0 62.0 58.6 - 6,49 562 to < 581
< 56.7
> 619 20-Jan-04 577.0 65.0 58.6-64.9 56.7 to < 58.6
< 561
> 64. 9 20-Oct-03 565.0 61.0 58.6-64.9 56.7 to < 58.6
< 517
> 619 25-Jul-03 567.0 60.5 58.6-64.9 56.7 to < 58.6
< 56.7
> 64.9 05-Ma -03 5650 61.0 58.6 - 6,19 562 to < 585
< 56.7
> 619 230a,03 5731 61.0 58.6-64.9 56.7 to < 58.6
< 56.7
> 619 21-Oct-02 572.0 61.0 58.6-64.9 563 to < 58.6
< 517
> 64.9 29-1/lay-01 576.0 62.0 58.6-64.9 56.7 to < 58.6
< 56.7
> 64.0 05-Mar-01 1 565.0 62.0 1
58.6-619 1560 to < 58.6 1§61
> 619