GNRO-2008/00035, Response to Request for Additional Information for Alternative No. VRR-GGNS-2007-02 from ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:* Entergy
{{#Wiki_filter:*
-===-                                                                                 Entergy Operations, Inc.
-===-Entergy GNRO-2008/00035 May 13, 2008 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Entergy Operations, Inc.
PO Box 756 Port Gibson, MS 39150 Tel 601 437 2800 GNRO-2008/00035 May 13, 2008 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Attention:     Document Control Desk SUbject:      Response to Request for Additional Information for Alternative No.
PO Box 756 Port Gibson, MS 39150 Tel 601 437 2800 Attention:
SUbject:
Document Control Desk Response to Request for Additional Information for Alternative No.
VRR-GGNS-2007-02 from ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
VRR-GGNS-2007-02 from ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29


==References:==
==References:==
: 1. Request for Alternative VRR-GGNS-2007-0"t and. VRR-GGNS-2007-02 Requests for Alternative from ASME OM Code 5-year Test Interval for Main Steam Safety Relief Valves, letter dated January 8, 2008, GNRO-2007/00076
1.
: 2. Grand Gulf Nuclear Station, Unit 1 - Request for Additional Information Regarding Request for Alternative No. VRR-GGNS-2007-02 From ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves (Tac No. MD7758), letter dated March 14, 2008, GNRI-2008/00035 Dear Sir or Madam'.
Request for Alternative VRR-GGNS-2007-0"t and. VRR-GGNS-2007-02 Requests for Alternative from ASME OM Code 5-year Test Interval for Main Steam Safety Relief Valves, {{letter dated|date=January 8, 2008|text=letter dated January 8, 2008}}, GNRO-2007/00076 2.
Grand Gulf Nuclear Station, Unit 1 - Request for Additional Information Regarding Request for Alternative No. VRR-GGNS-2007-02 From ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves (Tac No. MD7758), {{letter dated|date=March 14, 2008|text=letter dated March 14, 2008}}, GNRI-2008/00035 Dear Sir or Madam'.
In Reference 1, Grand Gulf requested relief from American Society of Mechanical Engineers Operation and Maintenance Code (ASME OM Code), 2001 Edition through 2003 Appendix, "Code of Operation and Maintenance of Nuclear Power Plants,"
In Reference 1, Grand Gulf requested relief from American Society of Mechanical Engineers Operation and Maintenance Code (ASME OM Code), 2001 Edition through 2003 Appendix, "Code of Operation and Maintenance of Nuclear Power Plants,"
Subsection ISTC, Mandatory Appendix I. Relief Request No. VRR-GGNS-2007-02 requested to extend the 5-year test interval, on a one-time basis, for eleven Main Steam Safety Relief Valves (SRVs) for Grand Gulf Nuclear Station, Unit 1 (GGNS). In Reference 2, the NRC transmitted a Request for Additional Information to Grand Gulf concerning the requested relief. The responses to Reference 2 are provided in the enclosure to this letter. This letter was delayed from the original 30 days as allowed by the Grand Gulf NRC Proiect Manager. l"he responses \\"1 tll\s letter are appl\cable \0 both Relief Requests VRR-GGNS-2007-01 and VRR-GGNS-2007-02 submitted in Reference 1.
Subsection ISTC, Mandatory Appendix I. Relief Request No. VRR-GGNS-2007-02 requested to extend the 5-year test interval, on a one-time basis, for eleven Main Steam Safety Relief Valves (SRVs) for Grand Gulf Nuclear Station, Unit 1 (GGNS). In Reference 2, the NRC transmitted a Request for Additional Information to Grand Gulf concerning the requested relief. The responses to Reference 2 are provided in the enclosure to this letter. This letter was delayed from the original 30 days as allowed by the Grand Gulf NRC Proiect Manager. l"he responses \\\\"1 tll\\s letter are appl\\cable \\0 both Relief Requests VRR-GGNS-2007-01 and VRR-GGNS-2007-02 submitted in Reference 1.
G080035
G080035


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==Enclosure:==
==Enclosure:==
Response to NRC Request for Additional Information -
cc:
VRR-GGNS-2007-02 cc:
G080035 Response to NRC Request for Additional Information -
NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATIN: Mr. Elmo E. Collins, Jr. (w/2) 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATIN: Mr. Jack N. Donohew, Jr., NRR/APROI DORL (w/2)
VRR-GGNS-2007-02 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATIN: Mr. Elmo E. Collins, Jr. (w/2) 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATIN: Mr. Jack N. Donohew, Jr., NRR/APROI DORL (w/2)
ATIN: ADDRESSEE ONLY ATIN: U. S. Postal Delivery Address Only Mail Stop OWFN/O-8G14 Washington, DC 20555-0001 G080035
ATIN: ADDRESSEE ONLY ATIN: U. S. Postal Delivery Address Only Mail Stop OWFN/O-8G14 Washington, DC 20555-0001


Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 The NRC transmitted a Request for Additional Information in a letter (Reference 2) dated March 14, 2008 to Grand Gulf concerning the requested relief. The response to the NRC requests shown below.
Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 The NRC transmitted a Request for Additional Information in a letter (Reference 2) dated March 14, 2008 to Grand Gulf concerning the requested relief. The response to the NRC requests shown below.
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===Response===
===Response===
The table below lists the refurbishment work orders and the installation work orders as verification that the Main Steam Safety Relief Valves (SRVs), were refurbished to a like-new condition prior to being placed in storage and later installed in the plant. During the time between refurbishment and installation, the valves were stored in metal storage containers in an indoor Class "C" storage area in accordance with ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants.
The table below lists the refurbishment work orders and the installation work orders as verification that the Main Steam Safety Relief Valves (SRVs), were refurbished to a like-new condition prior to being placed in storage and later installed in the plant. During the time between refurbishment and installation, the valves were stored in metal storage containers in an indoor Class "C" storage area in accordance with ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants.
Date         Refurbishment       Storage Duration           Date         Installation Valve Location     Serial Number       Refurbished       Work Order #                                 installed     Work Order 1B21F041K             160796             1/9/2004         50325284             21 months           10/3/2005         41320 1B21F041F             160836             1/9/2004         50325333             22 months           10/3/2005       50983208 1821F051F             160831             1/9/2004         50325330             22 months             10/3/2005       50983208 1B21F0518             160844             1/9/2004         50325287             22 months             10/3/2005       50983208 1B21F041D             160838             1/9/2004         50325286             22 months             10/3/2005       50983208 1B21F047D             160808             1/9/2004         50325285             23 months             10/3/2005       50983208 1821F047L             160825             1/25/2007           85663               2 months           3/21/2007       51034868 1B21 F041G           160819             9/13/2005           44310               18 months           3/21/2007       51034868 1B21F047G             160804             9/15/2005           44320               18 months           3/21/2007       51034868 1B21F051C             160812             9/15/2005           44309               18 months           3/21/2007       51034868 1B21F047C             160803             9/20/2005           44306               18 months             3/21/2007       51034868 G080035
Date Refurbishment Storage Duration Date Installation Valve Location Serial Number Refurbished Work Order #
installed Work Order 1B21F041K 160796 1/9/2004 50325284 21 months 10/3/2005 41320 1B21F041F 160836 1/9/2004 50325333 22 months 10/3/2005 50983208 1821F051F 160831 1/9/2004 50325330 22 months 10/3/2005 50983208 1B21F0518 160844 1/9/2004 50325287 22 months 10/3/2005 50983208 1B21F041D 160838 1/9/2004 50325286 22 months 10/3/2005 50983208 1B21F047D 160808 1/9/2004 50325285 23 months 10/3/2005 50983208 1821F047L 160825 1/25/2007 85663 2 months 3/21/2007 51034868 1B21 F041G 160819 9/13/2005 44310 18 months 3/21/2007 51034868 1B21F047G 160804 9/15/2005 44320 18 months 3/21/2007 51034868 1B21F051C 160812 9/15/2005 44309 18 months 3/21/2007 51034868 1B21F047C 160803 9/20/2005 44306 18 months 3/21/2007 51034868 G080035


Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 NRC Request #2 Discuss if the controlled environment for the storage of Valves 1B21-F041 K, 1B21-F041 F, 1B21-F051 F, 1B21-F051 B, 1B21-F041 D, 1B21-F047D, 1B21-F047L, 1B21-F041G, 1B21-F047G, 1B21-F051C, and 1B21-F047C was equipped to prevent condensation and corrosion.
Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 NRC Request #2 Discuss if the controlled environment for the storage of Valves 1B21-F041 K, 1B21-F041 F, 1B21-F051 F, 1B21-F051 B, 1B21-F041 D, 1B21-F047D, 1B21-F047L, 1B21-F041G, 1B21-F047G, 1B21-F051C, and 1B21-F047C was equipped to prevent condensation and corrosion.
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===Response===
===Response===
The valves in question are stored in an indoor Class C storage area in accordance with ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants. Class C storage areas are defined as follows:
The valves in question are stored in an indoor Class C storage area in accordance with ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants. Class C storage areas are defined as follows:
        "Level C items shall be stored indoors or equivalent with all the provisions and requirements set forth in Level B items except that heat and temperature control is not required. Level B items shall be stored within a fire resistant, tear resistant, weathertight, and well ventilated building or equivalent enclosures This area shall be situated and constructed so that it will not be subject to flooding; the floor shall be paved or equal, and well drained ltems shall be placed on shoring to permit circulation ... "
"Level C items shall be stored indoors or equivalent with all the provisions and requirements set forth in Level B items except that heat and temperature control is not required. Level B items shall be stored within a fire resistant, tear resistant, weathertight, and well ventilated building or equivalent enclosures This area shall be situated and constructed so that it will not be subject to flooding; the floor shall be paved or equal, and well drained ltems shall be placed on shoring to permit circulation... "
For the valves in question, each valve is stored in metal container. The seating surfaces between the metal container and the base of the container has a rubber gasket material, which seals the container, therefore while in storage the SRVs are protected from moisture. There has not been any indication of condensation or corrosion based on the current practice to store the valves in a Level C storage area coupled with sealing the valves in metal containers.
For the valves in question, each valve is stored in metal container. The seating surfaces between the metal container and the base of the container has a rubber gasket material, which seals the container, therefore while in storage the SRVs are protected from moisture. There has not been any indication of condensation or corrosion based on the current practice to store the valves in a Level C storage area coupled with sealing the valves in metal containers.
G080035
G080035


Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 NRC Request #3 Provide test results for Dikkers Model G-471 SRVs that were maintained in a controlled environment similar to the GGNS controlled environment for an extended period of time and setpoint tested prior to actual installation. As an alternative, discuss why the as-found set-pressure test results for Dikkers Model G-471 SRVs provided in a letter dated September 28,2007 (Agency wide ADAMS Accession No. ML072740030) are applicable to the GGNS SRVs.
Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 NRC Request #3 Provide test results for Dikkers Model G-471 SRVs that were maintained in a controlled environment similar to the GGNS controlled environment for an extended period of time and setpoint tested prior to actual installation. As an alternative, discuss why the as-found set-pressure test results for Dikkers Model G-471 SRVs provided in a {{letter dated|date=September 28, 2007|text=letter dated September 28,2007}} (Agency wide ADAMS Accession No. ML072740030) are applicable to the GGNS SRVs.


===Response===
===Response===
Grand Gulf is not aware of a situation in which a Grand Gulf SRV has been stored for an extended period, greater that two operation cycles, prior to being installed in the plant without the valve being inspected and recertified. The standard practice at Grand Gulf is to refurbish and certify valves no more that 30 months prior to installation in the plant. The table below show the Grand Gulf actual test result for SRVs test from RF11 (April 2001) through RF15 (February 2007). The table documents the time the valve was previously tested, date valve installed, and the as found testing results. For 21 of the tests, the as found pressure was found to be within 1% of the as left set pressure. One valve in this group of 21, serial number 160837 testing during RF14 (September 2005), had 97 months between test. This valve's as found test result was within 1% of the valves as left set pressure. The test results, summarized in the table below, confirms that the storage of for Dikkers Model G-471 SRVs for an extended period of time has minimal impact upon the ability of the SRVs to satisfy the ASME as found acceptance criteria of plus or minus 3%, and thus does not reduce the level of quality or safety.
Grand Gulf is not aware of a situation in which a Grand Gulf SRV has been stored for an extended period, greater that two operation cycles, prior to being installed in the plant without the valve being inspected and recertified. The standard practice at Grand Gulf is to refurbish and certify valves no more that 30 months prior to installation in the plant. The table below show the Grand Gulf actual test result for SRVs test from RF11 (April 2001) through RF15 (February 2007). The table documents the time the valve was previously tested, date valve installed, and the as found testing results. For 21 of the tests, the as found pressure was found to be within 1% of the as left set pressure. One valve in this group of 21, serial number 160837 testing during RF14 (September 2005), had 97 months between test. This valve's as found test result was within 1% of the valves as left set pressure. The test results, summarized in the table below, confirms that the storage of for Dikkers Model G-471 SRVs for an extended period of time has minimal impact upon the ability of the SRVs to satisfy the ASME as found acceptance criteria of plus or minus 3%, and thus does not reduce the level of quality or safety.
Outage f         Valve       Valve       Date of         Date     Date of       Time       Correlation   As Found         PSIG     % above of Work           Location     Serial     Previous     Installed in As Found     Between         Set       Test Result     above or     below set Order                       Number         Test         Plant       Test         Test       Pressure                     below set RF151 51034868 1B21F047L     160823     2/27/2001     10/02/2002 312512007   73 months       1199.91       1189           -10.91       -0.91%
Outage f Valve Valve Date of Date Date of Time Correlation As Found PSIG
1B21F041G     160800     9/11/2002     10/02/2002 3/25/2007   54 months       1184.32       1204           19.68         1.66%
% above of Work Location Serial Previous Installed in As Found Between Set Test Result above or below set Order Number Test Plant Test Test Pressure below set RF151 51034868 1B21F047L 160823 2/27/2001 10/02/2002 312512007 73 months 1199.91 1189
1B21 F047G     160826     2/27/2001     10/02/2002 3/25/2007   73 months     1199.44       1177           -22.44       -1.87%
-10.91
1B21F047C     160824     9/15/2005     10/03/2005 3/25/2007   18 months     1199.47       1209             9.53         0.80%
-0.91%
1B21F041C     160795     9/14/2005     10/03/2005 3/25/2007   18 months       1184.3       1189             4.7         0.40%
1B21F041G 160800 9/11/2002 10/02/2002 3/25/2007 54 months 1184.32 1204 19.68 1.66%
1B21F041A     160816     7/15/2002       3/15/2004 3/27/2007   56 months     1184.47       1183           -1.47       -0.12%
1B21 F047G 160826 2/27/2001 10/02/2002 3/25/2007 73 months 1199.44 1177
1B21F051A     160809     7/15/2002       3/15/2004 3/27/2007   56 months     1210.56       1219             8.44         0.70%
-22.44
RF141 I
-1.87%
50983208 1B21 F041 K   160801     3/14/2001       5/03/2001 9/25/2005   54 months     1183.96       1190             6.04         0.51%
1B21F047C 160824 9/15/2005 10/03/2005 3/25/2007 18 months 1199.47 1209 9.53 0.80%
1B21 F051 K   160832       1/9/2004     3/15/2004 9/25/2005   20 months     1209.35       1208           -1.35       -0.11 %
1B21F041C 160795 9/14/2005 10/03/2005 3/25/2007 18 months 1184.3 1189 4.7 0.40%
1B21F041F     160822     4/18/2001       5/03/2001 9/25/2005   53 months     1183.98       1189             5.02         0.42%
1B21F041A 160816 7/15/2002 3/15/2004 3/27/2007 56 months 1184.47 1183
1B21F051F     160834     4/18/2001       5/03/2001 9/25/2005   53 months     1209.33       1215             5.67         0.47%
-1.47
1B21F041B     160835     4/18/2001       5/03/2001 9/25/2005   53 months     1183.92       1186             2.08         0.18%
-0.12%
1B21F051B     160811     4/18/2001       5/03/2001 9/25/2005   53 months     1209.47       1223           13.53         1.12%
1B21F051A 160809 7/15/2002 3/15/2004 3/27/2007 56 months 1210.56 1219 8.44 0.70%
RF141 50983208 I
1B21 F041 K 160801 3/14/2001 5/03/2001 9/25/2005 54 months 1183.96 1190 6.04 0.51%
1B21 F051 K 160832 1/9/2004 3/15/2004 9/25/2005 20 months 1209.35 1208
-1.35
-0.11 %
1B21F041F 160822 4/18/2001 5/03/2001 9/25/2005 53 months 1183.98 1189 5.02 0.42%
1B21F051F 160834 4/18/2001 5/03/2001 9/25/2005 53 months 1209.33 1215 5.67 0.47%
1B21F041B 160835 4/18/2001 5/03/2001 9/25/2005 53 months 1183.92 1186 2.08 0.18%
1B21F051B 160811 4/18/2001 5/03/2001 9/25/2005 53 months 1209.47 1223 13.53 1.12%
G080035
G080035


Response to Request for Additional Information Relie f Request V RR-GGNS -2007 02 Time
Response to Request for Additional Information f
                                                                                              -Correlation                    PSIG Outage I                   Valve       Date of           Date       Date of Work           Valve       Serial     Previous     Installed in   As Found       Between       Set       As Found       above or % above of Order         Location   Number         Test           Plant         Test           Test     Pressure     Test Result     below set below set 1B21F041D     160837     8/4/1997       5/03/2001   9/25/2005     97 months     1184.14         1174         -1014     -0.86%
R GGNS 2007 02 Relie Request V R-Outage I Valve Date of Date Date of Time Correlation PSIG Work Valve Serial Previous Installed in As Found Between Set As Found above or
1821F047D     160825     3/30/1999       5/03/2001   9/25/2005     78 months     1199.36         1157         -42.36     -3.53%
% above of Order Location Number Test Plant Test Test Pressure Test Result below set below set 1B21F041D 160837 8/4/1997 5/03/2001 9/25/2005 97 months 1184.14 1174
1B21F051C     160830     9/18/2002       10102/2002   912512005     36 months     1209.35         1196         -13.35     -1.10%
-1014
-0.86%
1821F047D 160825 3/30/1999 5/03/2001 9/25/2005 78 months 1199.36 1157
-42.36
-3.53%
1B21F051C 160830 9/18/2002 10102/2002 912512005 36 months 1209.35 1196
-13.35
-1.10%
RF13/
RF13/
50336965 1821F041A     160815     12/12/1997     12/04/1999     313/2004     75 months   1184.63         1180           -4.63   -0.39%
50336965 1821F041A 160815 12/12/1997 12/04/1999 313/2004 75 months 1184.63 1180
1821F041E     160795     12/30/1997     12/04/1999     313/2004     75 months   1184.71         1165         -19.71     -1.66%
-4.63
1821F047A     160804     5/6/1999       12104/1999     313/2004     58 months   1199.97         1193           -6.97   -0.58%
-0.39%
1821 F047H   160839     3/30/1999     12/04/1999     3/3/2004     60 months   1199.93         1183         -16.93     -1.41%
1821F041E 160795 12/30/1997 12/04/1999 313/2004 75 months 1184.71 1165
1821F051A     160829       1/6/1998     12104/1999     313/2004     74 months   1210.12         1190         -20.12   -1.67%
-19.71
1821F051D     160813     2/17/1999     12/04/1999     3/3/2004     61 months   1210.03         1183         -27.03   -2.23%
-1.66%
1821F047A 160804 5/6/1999 12104/1999 313/2004 58 months 1199.97 1193
-6.97
-0.58%
1821 F047H 160839 3/30/1999 12/04/1999 3/3/2004 60 months 1199.93 1183
-16.93
-1.41%
1821F051A 160829 1/6/1998 12104/1999 313/2004 74 months 1210.12 1190
-20.12
-1.67%
1821F051D 160813 2/17/1999 12/04/1999 3/3/2004 61 months 1210.03 1183
-27.03
-2.23%
RF12/
RF12/
MAI311478 1821F041C     160802     12/3/1997       5108/1998   9/22/2002     57 months   1184.69         1216         31.31     2.60%
MAI311478 1821F041C 160802 12/3/1997 5108/1998 9/22/2002 57 months 1184.69 1216 31.31 2.60%
1821F047C     160841     11/13/1997       510811998   9/22/2002     58 months   1199.79         1209           9.21     0.40%
1821F047C 160841 11/13/1997 510811998 9/22/2002 58 months 1199.79 1209 9.21 0.40%
1B21F051C     160814     11/21/1997       510811998   9/22/2002     58 months   1210.03         1225           14.97     1.30%
1B21F051C 160814 11/21/1997 510811998 9/22/2002 58 months 1210.03 1225 14.97 1.30%
1821F047L     160827     11/12/1997       5/0811998   9/22/2002     58 months   1199.83         1193           -6.83   -0.50%
1821F047L 160827 11/12/1997 5/0811998 9/22/2002 58 months 1199.83 1193
1821 F047G   160824     12/18/1997       5108/1998     9/22/2002     57 months   1199.89         1194           -5.89   -0.49%
-6.83
1821F041G     160818     11/28/1997       5/08/1998     9/22/2002     58 months   1184.49         1174         -10.49   -0.89%
-0.50%
1821 F047G 160824 12/18/1997 5108/1998 9/22/2002 57 months 1199.89 1194
-5.89
-0.49%
1821F041G 160818 11/28/1997 5/08/1998 9/22/2002 58 months 1184.49 1174
-10.49
-0.89%
RF11/
RF11/
MAI287068 Steam Set     As-found
MAI287068 Steam Set As-found Pressure Result 1821F047D 160840 5/1/1995 10/22/1996 4/3012001 73 months 1180 1207 27 2.29%
* Pressure       Result 1821F047D     160840       5/1/1995     10/22/1996   4/3012001     73 months     1180         1207             27     2.29%
1B21F041D 160817 5/11/1995 10/22/1996 4/30/2001 73 months 1165 1172 7
1B21F041D     160817     5/11/1995     10/22/1996     4/30/2001     73 months     1165         1172             7     0.60%
0.60%
1821F041K     160800     5/18/1995     10/22/1996     4/30/2001     73 months     1165         1166             1     0.09%
1821F041K 160800 5/18/1995 10/22/1996 4/30/2001 73 months 1165 1166 1
1821F051K     160830     5/16/1995     10/22/1996     4/30/2001     73 months     1190         1202             12     1.00%
0.09%
1B21F041F     160821       5/5/1995     10/22/1996     4/30/2001     73 months     1165         1175             10     0.86%
1821F051K 160830 5/16/1995 10/22/1996 4/30/2001 73 months 1190 1202 12 1.00%
1821F051F     160809     5/15/1995     10/22/1996     4/3012001     73 months     1190         1200             10     0.84%
1B21F041F 160821 5/5/1995 10/22/1996 4/30/2001 73 months 1165 1175 10 0.86%
1821F0418     160816     5/17/1995     10/22/1996     4/3012001     73 months     1165           1180           15     1.29%
1821F051F 160809 5/15/1995 10/22/1996 4/3012001 73 months 1190 1200 10 0.84%
1821F0518     160810     5/15/1995     10/22/1996     4/3012001     73 months     1190           1209           19     1.60%
1821F0418 160816 5/17/1995 10/22/1996 4/3012001 73 months 1165 1180 15 1.29%
1821F0518 160810 5/15/1995 10/22/1996 4/3012001 73 months 1190 1209 19 1.60%
Note: RF11 valves were set and tested by the use of steam, not nitrogen
Note: RF11 valves were set and tested by the use of steam, not nitrogen
* See PO #NHS00370 for pressure see results 8080035}}
* See PO #NHS00370 for pressure see results 8080035}}

Latest revision as of 16:46, 14 January 2025

Response to Request for Additional Information for Alternative No. VRR-GGNS-2007-02 from ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves
ML081350061
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 05/13/2008
From: Larson M
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2008/00035
Download: ML081350061 (6)
v • d • e


Text

-===-Entergy GNRO-2008/00035 May 13, 2008 U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Entergy Operations, Inc.

PO Box 756 Port Gibson, MS 39150 Tel 601 437 2800 Attention:

SUbject:

Document Control Desk Response to Request for Additional Information for Alternative No.

VRR-GGNS-2007-02 from ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

References:

1.

Request for Alternative VRR-GGNS-2007-0"t and. VRR-GGNS-2007-02 Requests for Alternative from ASME OM Code 5-year Test Interval for Main Steam Safety Relief Valves, "GNRO-2007/00076, Request for Alternative VRR-GGNS-2007-01 and VRR-GGNS-2007-02 Requests for Alternative from ASME OM Code 5-Year Test Interval for Main Steam [[system" contains a listed "[" character as part of the property label and has therefore been classified as invalid.s|letter dated January 8, 2008]], GNRO-2007/00076 2.

Grand Gulf Nuclear Station, Unit 1 - Request for Additional Information Regarding Request for Alternative No. VRR-GGNS-2007-02 From ASME OM Code 5-Year Test Interval for Main Steam Safety Relief Valves (Tac No. MD7758), letter dated March 14, 2008, GNRI-2008/00035 Dear Sir or Madam'.

In Reference 1, Grand Gulf requested relief from American Society of Mechanical Engineers Operation and Maintenance Code (ASME OM Code), 2001 Edition through 2003 Appendix, "Code of Operation and Maintenance of Nuclear Power Plants,"

Subsection ISTC, Mandatory Appendix I. Relief Request No. VRR-GGNS-2007-02 requested to extend the 5-year test interval, on a one-time basis, for eleven Main Steam Safety Relief Valves (SRVs) for Grand Gulf Nuclear Station, Unit 1 (GGNS). In Reference 2, the NRC transmitted a Request for Additional Information to Grand Gulf concerning the requested relief. The responses to Reference 2 are provided in the enclosure to this letter. This letter was delayed from the original 30 days as allowed by the Grand Gulf NRC Proiect Manager. l"he responses \\\\"1 tll\\s letter are appl\\cable \\0 both Relief Requests VRR-GGNS-2007-01 and VRR-GGNS-2007-02 submitted in Reference 1.

G080035

GNRO-2008/00035 Page 2 Entergy requests approval of Relief Request VRR-GGNS-2007-02 by July 11, 2008 to enable startup of GGNS Unit 1 following RF-16 in Fall of 2008, and continued operation until the seventeenth refueling outage (RF-17) and the eighteenth refueling outage (RF-18). RF-17 is currently scheduled to begin in Spring of 2010 and RF-18 is scheduled to begin in Winter of 2012.

This letter contains no commitments.

Should you have any questions regarding this submittal, please contact Michael Larson at (601) 437-6685.

Sincerely, Michael J. Larson Acting Licensing Manager MJL:mjl

Enclosure:

cc:

G080035 Response to NRC Request for Additional Information -

VRR-GGNS-2007-02 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATIN: Mr. Elmo E. Collins, Jr. (w/2) 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATIN: Mr. Jack N. Donohew, Jr., NRR/APROI DORL (w/2)

ATIN: ADDRESSEE ONLY ATIN: U. S. Postal Delivery Address Only Mail Stop OWFN/O-8G14 Washington, DC 20555-0001

Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 The NRC transmitted a Request for Additional Information in a letter (Reference 2) dated March 14, 2008 to Grand Gulf concerning the requested relief. The response to the NRC requests shown below.

NRC Request #1 Verify that Valves 1B21-F041 K, 1B21-F041 F, 1B21-F051 F, 1B21-F051 B, 1B21-F041 D, and 1B21-F047D were refurbished to a like-new condition prior to being placed in storage and later installed in October 2005. Verify that Valves 1B21-F047L, 1B21-F041G, 1B21-F047G, 1B21-F051 C, and 1B21-F047C were refurbished to a like-new condition prior to being placed in storage and later installed in March 2007.

Response

The table below lists the refurbishment work orders and the installation work orders as verification that the Main Steam Safety Relief Valves (SRVs), were refurbished to a like-new condition prior to being placed in storage and later installed in the plant. During the time between refurbishment and installation, the valves were stored in metal storage containers in an indoor Class "C" storage area in accordance with ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants.

Date Refurbishment Storage Duration Date Installation Valve Location Serial Number Refurbished Work Order #

installed Work Order 1B21F041K 160796 1/9/2004 50325284 21 months 10/3/2005 41320 1B21F041F 160836 1/9/2004 50325333 22 months 10/3/2005 50983208 1821F051F 160831 1/9/2004 50325330 22 months 10/3/2005 50983208 1B21F0518 160844 1/9/2004 50325287 22 months 10/3/2005 50983208 1B21F041D 160838 1/9/2004 50325286 22 months 10/3/2005 50983208 1B21F047D 160808 1/9/2004 50325285 23 months 10/3/2005 50983208 1821F047L 160825 1/25/2007 85663 2 months 3/21/2007 51034868 1B21 F041G 160819 9/13/2005 44310 18 months 3/21/2007 51034868 1B21F047G 160804 9/15/2005 44320 18 months 3/21/2007 51034868 1B21F051C 160812 9/15/2005 44309 18 months 3/21/2007 51034868 1B21F047C 160803 9/20/2005 44306 18 months 3/21/2007 51034868 G080035

Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 NRC Request #2 Discuss if the controlled environment for the storage of Valves 1B21-F041 K, 1B21-F041 F, 1B21-F051 F, 1B21-F051 B, 1B21-F041 D, 1B21-F047D, 1B21-F047L, 1B21-F041G, 1B21-F047G, 1B21-F051C, and 1B21-F047C was equipped to prevent condensation and corrosion.

Response

The valves in question are stored in an indoor Class C storage area in accordance with ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants. Class C storage areas are defined as follows:

"Level C items shall be stored indoors or equivalent with all the provisions and requirements set forth in Level B items except that heat and temperature control is not required. Level B items shall be stored within a fire resistant, tear resistant, weathertight, and well ventilated building or equivalent enclosures This area shall be situated and constructed so that it will not be subject to flooding; the floor shall be paved or equal, and well drained ltems shall be placed on shoring to permit circulation... "

For the valves in question, each valve is stored in metal container. The seating surfaces between the metal container and the base of the container has a rubber gasket material, which seals the container, therefore while in storage the SRVs are protected from moisture. There has not been any indication of condensation or corrosion based on the current practice to store the valves in a Level C storage area coupled with sealing the valves in metal containers.

G080035

Response to Request for Additional Information Relief Request VRR-GGNS-2007-02 NRC Request #3 Provide test results for Dikkers Model G-471 SRVs that were maintained in a controlled environment similar to the GGNS controlled environment for an extended period of time and setpoint tested prior to actual installation. As an alternative, discuss why the as-found set-pressure test results for Dikkers Model G-471 SRVs provided in a letter dated September 28,2007 (Agency wide ADAMS Accession No. ML072740030) are applicable to the GGNS SRVs.

Response

Grand Gulf is not aware of a situation in which a Grand Gulf SRV has been stored for an extended period, greater that two operation cycles, prior to being installed in the plant without the valve being inspected and recertified. The standard practice at Grand Gulf is to refurbish and certify valves no more that 30 months prior to installation in the plant. The table below show the Grand Gulf actual test result for SRVs test from RF11 (April 2001) through RF15 (February 2007). The table documents the time the valve was previously tested, date valve installed, and the as found testing results. For 21 of the tests, the as found pressure was found to be within 1% of the as left set pressure. One valve in this group of 21, serial number 160837 testing during RF14 (September 2005), had 97 months between test. This valve's as found test result was within 1% of the valves as left set pressure. The test results, summarized in the table below, confirms that the storage of for Dikkers Model G-471 SRVs for an extended period of time has minimal impact upon the ability of the SRVs to satisfy the ASME as found acceptance criteria of plus or minus 3%, and thus does not reduce the level of quality or safety.

Outage f Valve Valve Date of Date Date of Time Correlation As Found PSIG

% above of Work Location Serial Previous Installed in As Found Between Set Test Result above or below set Order Number Test Plant Test Test Pressure below set RF151 51034868 1B21F047L 160823 2/27/2001 10/02/2002 312512007 73 months 1199.91 1189

-10.91

-0.91%

1B21F041G 160800 9/11/2002 10/02/2002 3/25/2007 54 months 1184.32 1204 19.68 1.66%

1B21 F047G 160826 2/27/2001 10/02/2002 3/25/2007 73 months 1199.44 1177

-22.44

-1.87%

1B21F047C 160824 9/15/2005 10/03/2005 3/25/2007 18 months 1199.47 1209 9.53 0.80%

1B21F041C 160795 9/14/2005 10/03/2005 3/25/2007 18 months 1184.3 1189 4.7 0.40%

1B21F041A 160816 7/15/2002 3/15/2004 3/27/2007 56 months 1184.47 1183

-1.47

-0.12%

1B21F051A 160809 7/15/2002 3/15/2004 3/27/2007 56 months 1210.56 1219 8.44 0.70%

RF141 50983208 I

1B21 F041 K 160801 3/14/2001 5/03/2001 9/25/2005 54 months 1183.96 1190 6.04 0.51%

1B21 F051 K 160832 1/9/2004 3/15/2004 9/25/2005 20 months 1209.35 1208

-1.35

-0.11 %

1B21F041F 160822 4/18/2001 5/03/2001 9/25/2005 53 months 1183.98 1189 5.02 0.42%

1B21F051F 160834 4/18/2001 5/03/2001 9/25/2005 53 months 1209.33 1215 5.67 0.47%

1B21F041B 160835 4/18/2001 5/03/2001 9/25/2005 53 months 1183.92 1186 2.08 0.18%

1B21F051B 160811 4/18/2001 5/03/2001 9/25/2005 53 months 1209.47 1223 13.53 1.12%

G080035

Response to Request for Additional Information f

R GGNS 2007 02 Relie Request V R-Outage I Valve Date of Date Date of Time Correlation PSIG Work Valve Serial Previous Installed in As Found Between Set As Found above or

% above of Order Location Number Test Plant Test Test Pressure Test Result below set below set 1B21F041D 160837 8/4/1997 5/03/2001 9/25/2005 97 months 1184.14 1174

-1014

-0.86%

1821F047D 160825 3/30/1999 5/03/2001 9/25/2005 78 months 1199.36 1157

-42.36

-3.53%

1B21F051C 160830 9/18/2002 10102/2002 912512005 36 months 1209.35 1196

-13.35

-1.10%

RF13/

50336965 1821F041A 160815 12/12/1997 12/04/1999 313/2004 75 months 1184.63 1180

-4.63

-0.39%

1821F041E 160795 12/30/1997 12/04/1999 313/2004 75 months 1184.71 1165

-19.71

-1.66%

1821F047A 160804 5/6/1999 12104/1999 313/2004 58 months 1199.97 1193

-6.97

-0.58%

1821 F047H 160839 3/30/1999 12/04/1999 3/3/2004 60 months 1199.93 1183

-16.93

-1.41%

1821F051A 160829 1/6/1998 12104/1999 313/2004 74 months 1210.12 1190

-20.12

-1.67%

1821F051D 160813 2/17/1999 12/04/1999 3/3/2004 61 months 1210.03 1183

-27.03

-2.23%

RF12/

MAI311478 1821F041C 160802 12/3/1997 5108/1998 9/22/2002 57 months 1184.69 1216 31.31 2.60%

1821F047C 160841 11/13/1997 510811998 9/22/2002 58 months 1199.79 1209 9.21 0.40%

1B21F051C 160814 11/21/1997 510811998 9/22/2002 58 months 1210.03 1225 14.97 1.30%

1821F047L 160827 11/12/1997 5/0811998 9/22/2002 58 months 1199.83 1193

-6.83

-0.50%

1821 F047G 160824 12/18/1997 5108/1998 9/22/2002 57 months 1199.89 1194

-5.89

-0.49%

1821F041G 160818 11/28/1997 5/08/1998 9/22/2002 58 months 1184.49 1174

-10.49

-0.89%

RF11/

MAI287068 Steam Set As-found Pressure Result 1821F047D 160840 5/1/1995 10/22/1996 4/3012001 73 months 1180 1207 27 2.29%

1B21F041D 160817 5/11/1995 10/22/1996 4/30/2001 73 months 1165 1172 7

0.60%

1821F041K 160800 5/18/1995 10/22/1996 4/30/2001 73 months 1165 1166 1

0.09%

1821F051K 160830 5/16/1995 10/22/1996 4/30/2001 73 months 1190 1202 12 1.00%

1B21F041F 160821 5/5/1995 10/22/1996 4/30/2001 73 months 1165 1175 10 0.86%

1821F051F 160809 5/15/1995 10/22/1996 4/3012001 73 months 1190 1200 10 0.84%

1821F0418 160816 5/17/1995 10/22/1996 4/3012001 73 months 1165 1180 15 1.29%

1821F0518 160810 5/15/1995 10/22/1996 4/3012001 73 months 1190 1209 19 1.60%

Note: RF11 valves were set and tested by the use of steam, not nitrogen

  • See PO #NHS00370 for pressure see results 8080035
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