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{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 16, 2012 U.S. Nuclear Regulatory Commission Attention:
{{#Wiki_filter:VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 16, 2012 U.S. Nuclear Regulatory Commission                               Serial No.:      12-083 Attention: Document Control Desk                                 NAPS/JHL:        RO Washington, D.C. 20555                                           Docket No.:     50-339 License No.:     NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
Document Control Desk Washington, D.C. 20555 Serial No.: NAPS/JHL: Docket No.: License No.: 12-083 RO 50-339 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)
NORTH ANNA POWER STATION UNIT 2 OWNER'S ACTIVITY REPORT In accordance with the requirements of American Society of Mechanical Engineers (ASME) Code Case N-532-4, enclosed is the Owner's Activity Report (Form OAR-I), for refueling outage N2R21. This report is for the first refueling outage of the first period of the fourth inspection interval.
NORTH ANNA POWER STATION UNIT 2 OWNER'S ACTIVITY REPORT In accordance with the requirements of American Society of Mechanical Engineers (ASME) Code Case N-532-4, enclosed is the Owner's Activity Report (Form OAR-I), for refueling outage N2R21. This report is for the first refueling outage of the first period of the fourth inspection interval.Should you have any questions regarding this submittal, please contact Mr. Donald R.Taylor at (540) 894-2616.Very truly yours,:. -F. Mladen Director -Nuclear Station Safety and Licensing Commitments made in this letter: None Attachment ocl Q U P.cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.Suite 300 Glen Allen, Virginia 23060 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Mr. M. M. Grace Authorized Nuclear Inspector North Anna Power Station W Attachment Owner's Activity Reports for North Anna Unit 2 Refueling Outage N2R21 -First Period of the Fourth ISI Interval Virginia Electric and Power Company (Dominion)  
Should you have any questions regarding this submittal, please contact Mr. Donald R.
&OFDominion-Form OAR-I, Owner's Activity Report E-,A-S-0 ATAHET PaeIo Report Number: N2R21 (Unit 1, 4th Interval, 1 a Period)Plant: North Anna Power Station Unit No. 2f (if applicable)
Taylor at (540) 894-2616.
Commercial service date: 12/14/1980 Refueling outage no. N2R21 Current inspection interval:
Very truly yours,
4t" (December 14, 2010 -December 13, 2020)(16, 2no, 3 T, 4 t , other)Current inspection period: 1 " (December 14,.2010 -December 13, 2013)(19, 2no, 3rd, 4e1)Edition and Addenda of Section XA applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: Revision 1. February 2011 Edition and Addenda of Section XA applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-432-1. N-460, N-504-3. N-526, N-532-4. N-552, N-566-2. N-586-1, N-597-2. N-61 3-1.N-624, N-638-1, N-641, N-651, N-658, N-661, N-663, N-683, N-696, N-706-1, N-722, and N-729-1 (if applicable)
:. -
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made In this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xi; and (c) the repair/replacement actUvities and evaluations supporting the completion of N2R21 conform to the requirements of Section XI.(refueling outage number)Signed Owner or Owner's Desine il Date 9 -/Z CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Virginla and employed by HSB CT of Hartford, CT have inspected the items described In this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection.
F. Mladen Director - Nuclear Station Safety and Licensing Commitments made in this letter: None Attachment ocl Q U
_ _ Cm Commissions NB 9531-A-N-I-C I VA 424-R Inspector's'Signature National Board, State, Province and Endorsements Date /, 3' L'-'-/2, ZtZ , Form No. 729596 (Aug 2009)
 
WDominion-Form OAR-1, Owner's Activity Report ER-l AISI10 AT ... TA HM N I ae A2o Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number H-603A Sway Strut for 2-SI-P- Eval per CR442495 for 1B improperly seated snap ring F-A / F1.40A does not impact the ability of the support to perform its design function in both normal or abnormal conditions.
P.
Summary # N2.F1.40.090 Snubber, 2-SI-HSS-809B 2 PSI found missing spacers, eval by CR442392 F-A / F1.20D verified that missing spacer does not impact ability of Summary# N2.F1.20.1 19 snubber to perform its function or provide support.Snubber 2-SI-HSS-421.02 CR442784, missing spacer on piston rod clevis pin, verified F-Al FI.IOD that missing spacer does not impact ability of snubber to#N2.11.10.095 perform its function or provide Summary# Nsupport.Snubber 2-RH-HSS-102 CR443946, loose bolt on pipe clamp, low fluid, tested SAT, F-A/ Fl.20D no slipping, evaluated as functional.
cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.
Performed additional examinations
Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.
-Summary # N2.F1 .20.371 ST SAT.Attachment Weld 12H *CR444219, Relevant indication found. CC N-586-1 B-KI B10.20 evaluation, construction flaw at surface. Ground out, Summary # N2.B10.20.001 teedST tested SAT.Snubber 2-RC-HSS-459.01 CR444443, snubber & pipe F-A /FI. 1OD clamp alignment/binding, Summary # N2.F1.10.222 tested SAT RPVH Pens #8, 15, and 23 CR443870, discoloration and B-E / B4.30 staining, cleaned and found no degradation.
Suite 300 Glen Allen, Virginia 23060 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Mr. M. M. Grace Authorized Nuclear Inspector North Anna Power Station
Evaluated Summary # N2.B4.30.001 SAT.RPVH Pen #18 CR444072, canopy seal weld B-E / B4.30 leakage from above, boric Summary # N2.134.30.001 acid residue, no degradation RPVH Pen #41 CR444091, residue from B-E I B4.30 canopy seal identified at pen Form No. 729595 (Aug 2009)
 
Dftminion-Form OAR-I, Owner's Activity Report ERAA-S-0 ATTACMN I ae3o Summary# N2.B4.30.001  
W Attachment Owner's Activity Reports for North Anna Unit 2 Refueling Outage N2R21 - First Period of the Fourth ISI Interval Virginia Electric and Power Company (Dominion)
#18, no degradation Spring Hanger SH-1 CR446060, owner elected F-A / FI. 1OC examination found loose nut, evaluated as able to perform Summary# N2.Fl.10.263 design function Restraint R-537 CR444413, PSI found F-A / F1.20B clearance issue, evaluation determined within the Summary # N2.F1.20.253 standard.CR448737, rub marks and no Reactor Vessel Pad Support-5 measurable gap on one side.No depth or displaced metal, F-A I F1.40B free to move, permits thermal growth and restrains in lateral Summary # N2.F1 .40.067 and vertical direction, meets function.Form No. 729595 (Aug 2009)
 
WDominion-Form OAR-I, Owner's Activity Report Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Date Repair/Replacement Class Item Description Description of Work Completed Plan Number Snubber, 2-RC- 2nd preservice found 1 HSS-455.012preicfon 1 welded lug to anchor 2011-110 F-A / for paddle pin bent 11/6/2011 2011-120 F1.10D Summary# downward, N2.Fl.10.486 CR442774.2"-WS-485-164-Q3 Replace 2" piping due 11/17/2011 2011-172 D-B / D2.10 downstream of 2- to MIC leak at weld SW-212 Form No. 729595 (Aug 2009)}}
Form OAR-I, Owner's Activity Report
&OFDominion-                                      E-,A-S-0                     ATAHET                       PaeIo Report Number: N2R21 (Unit 1, 4th Interval, 1 a Period)
Plant: North Anna Power Station Unit No.           2f               Commercial service date: 12/14/1980                   Refueling outage no. N2R21 (if applicable)
Current inspection interval: 4t" (December 14, 2010 - December 13, 2020)
(16, 2no, 3T, 4 t , other)
Current inspection period: 1" (December 14,.2010 - December 13, 2013)
(19, 2no, 3rd, 4e1)
Edition and Addenda of Section XA applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: Revision 1. February 2011 Edition and Addenda of Section XA applicable to repair/replacement activities, if different than the inspection plans           N/A Code Cases used: N-432-1. N-460, N-504-3. N-526, N-532-4. N-552, N-566-2. N-586-1, N-597-2. N-61 3-1.
N-624, N-638-1, N-641, N-651, N-658, N-661, N-663, N-683, N-696, N-706-1, N-722, and N-729-1 (if applicable)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made In this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xi; and (c) the repair/replacement actUvities and evaluations supporting the completion of N2R21                                 conform to the requirements of Section XI.
(refueling outage number)
Signed                                                                                           Date  9-/Z Owner or Owner's Desine         il CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Virginla                         and employed by HSB CT               of Hartford, CT have inspected the items described In this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.
By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection.
_         _           Cm                     Commissions     NB 9531-A-N-I-C I VA 424-R Inspector's'Signature                                             National Board, State, Province and Endorsements Date     /, 3'   L'-'-/2,ZtZ           ,
Form No. 729596 (Aug 2009)
 
Form OAR-1, Owner's Activity Report AT              I            ae WDominion-                            ER-l   AISI10       ...
TA HM   N                               A2o Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination                 Item Description               Evaluation Description Category and Item Number H-603A Sway Strut for 2-SI-P-     Eval per CR442495 for 1B                               improperly seated snap ring F-A / F1.40A                                           does not impact the ability of the support to perform its design function in both normal Summary # N2.F1.40.090           or abnormal conditions.
Snubber, 2-SI-HSS-809B           2 PSI found missing spacers, eval by CR442392 F-A / F1.20D                                           verified that missing spacer does not impact ability of Summary# N2.F1.20.1 19           snubber to perform its function or provide support.
Snubber 2-SI-HSS-421.02           CR442784, missing spacer on piston rod clevis pin, verified F-Al FI.IOD                                             that missing spacer does not impact ability of snubber to
                                            #N2.11.10.095       perform its function or provide Summary# Nsupport.
Snubber 2-RH-HSS-102             CR443946, loose bolt on pipe clamp, low fluid, tested SAT, F-A/ Fl.20D                                             no slipping, evaluated as functional. Performed Summary # N2.F1 .20.371           additional examinations -
ST SAT.
Attachment Weld 12H *CR444219,                 Relevant indication found. CC N-586-1 B-KI B10.20                                             evaluation, construction flaw Summary # N2.B10.20.001           at  surface. Ground out, teedST tested SAT.
Snubber 2-RC-HSS-459.01           CR444443, snubber & pipe F-A /FI. 1OD                                           clamp alignment/binding, Summary # N2.F1.10.222           tested SAT RPVH Pens #8, 15, and 23         CR443870, discoloration and B-E / B4.30                                             staining, cleaned and found no degradation. Evaluated Summary # N2.B4.30.001           SAT.
RPVH Pen #18                     CR444072, canopy seal weld B-E / B4.30                                             leakage from above, boric Summary # N2.134.30.001           acid residue, no degradation RPVH Pen #41                     CR444091, residue from B-E I B4.30                                             canopy seal identified at pen Form No. 729595 (Aug 2009)
 
Form OAR-I, Owner's Activity Report Dftminion-            ERAA-S-0           ATTACMN           I           ae3o Summary# N2.B4.30.001           #18, no degradation Spring Hanger SH-1             CR446060, owner elected F-A / FI. 1OC                                 examination found loose nut, evaluated as able to perform Summary# N2.Fl.10.263           design function Restraint R-537                 CR444413, PSI found F-A / F1.20B                                 clearance issue, evaluation determined within the Summary # N2.F1.20.253         standard.
CR448737, rub marks and no Reactor Vessel Pad Support-5   measurable gap on one side.
No depth or displaced metal, F-A I F1.40B                                 free to move, permits thermal growth and restrains in lateral Summary # N2.F1 .40.067         and vertical direction, meets function.
Form No. 729595 (Aug 2009)
 
Form OAR-I, Owner's Activity Report WDominion-Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code                                                     Date       Repair/Replacement Class     Item Description   Description of Work   Completed       Plan Number Snubber, 2-RC-     2nd preservice found 1 HSS-455.012preicfon 1                   welded lug to anchor                 2011-110 F-A /                         for paddle pin bent   11/6/2011     2011-120 F1.10D     Summary#           downward, N2.Fl.10.486       CR442774.
2"-WS-485-164-Q3   Replace 2" piping due 11/17/2011   2011-172 D-B / D2.10 downstream of 2-   to MIC leak at weld SW-212 Form No. 729595 (Aug 2009)}}

Revision as of 08:26, 12 November 2019

Owner'S Activity Report for Refueling Outage N2R21
ML12060A349
Person / Time
Site: North Anna Dominion icon.png
Issue date: 02/16/2012
From: Mladen F
Virginia Electric & Power Co (VEPCO), Dominion
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
12-083
Download: ML12060A349 (7)


Text

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 16, 2012 U.S. Nuclear Regulatory Commission Serial No.: 12-083 Attention: Document Control Desk NAPS/JHL: RO Washington, D.C. 20555 Docket No.: 50-339 License No.: NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

NORTH ANNA POWER STATION UNIT 2 OWNER'S ACTIVITY REPORT In accordance with the requirements of American Society of Mechanical Engineers (ASME) Code Case N-532-4, enclosed is the Owner's Activity Report (Form OAR-I), for refueling outage N2R21. This report is for the first refueling outage of the first period of the fourth inspection interval.

Should you have any questions regarding this submittal, please contact Mr. Donald R.

Taylor at (540) 894-2616.

Very truly yours,

. -

F. Mladen Director - Nuclear Station Safety and Licensing Commitments made in this letter: None Attachment ocl Q U

P.

cc: U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE, Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector North Anna Power Station Mr. J. E. Reasor, Jr.

Old Dominion Electric Cooperative Innsbrook Corporate Center 4201 Dominion Blvd.

Suite 300 Glen Allen, Virginia 23060 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 Mr. M. M. Grace Authorized Nuclear Inspector North Anna Power Station

W Attachment Owner's Activity Reports for North Anna Unit 2 Refueling Outage N2R21 - First Period of the Fourth ISI Interval Virginia Electric and Power Company (Dominion)

Form OAR-I, Owner's Activity Report

&OFDominion- E-,A-S-0 ATAHET PaeIo Report Number: N2R21 (Unit 1, 4th Interval, 1 a Period)

Plant: North Anna Power Station Unit No. 2f Commercial service date: 12/14/1980 Refueling outage no. N2R21 (if applicable)

Current inspection interval: 4t" (December 14, 2010 - December 13, 2020)

(16, 2no, 3T, 4 t , other)

Current inspection period: 1" (December 14,.2010 - December 13, 2013)

(19, 2no, 3rd, 4e1)

Edition and Addenda of Section XA applicable to the inspection plans: 2004 Edition with No Addenda Date and revision of inspection plans: Revision 1. February 2011 Edition and Addenda of Section XA applicable to repair/replacement activities, if different than the inspection plans N/A Code Cases used: N-432-1. N-460, N-504-3. N-526, N-532-4. N-552, N-566-2. N-586-1, N-597-2. N-61 3-1.

N-624, N-638-1, N-641, N-651, N-658, N-661, N-663, N-683, N-696, N-706-1, N-722, and N-729-1 (if applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made In this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xi; and (c) the repair/replacement actUvities and evaluations supporting the completion of N2R21 conform to the requirements of Section XI.

(refueling outage number)

Signed Date 9-/Z Owner or Owner's Desine il CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Virginla and employed by HSB CT of Hartford, CT have inspected the items described In this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.

By signing this certificate neither the inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage or a loss of any kind arising from or connected with this inspection.

_ _ Cm Commissions NB 9531-A-N-I-C I VA 424-R Inspector's'Signature National Board, State, Province and Endorsements Date /, 3' L'-'-/2,ZtZ ,

Form No. 729596 (Aug 2009)

Form OAR-1, Owner's Activity Report AT I ae WDominion- ER-l AISI10 ...

TA HM N A2o Table I Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Item Description Evaluation Description Category and Item Number H-603A Sway Strut for 2-SI-P- Eval per CR442495 for 1B improperly seated snap ring F-A / F1.40A does not impact the ability of the support to perform its design function in both normal Summary # N2.F1.40.090 or abnormal conditions.

Snubber, 2-SI-HSS-809B 2 PSI found missing spacers, eval by CR442392 F-A / F1.20D verified that missing spacer does not impact ability of Summary# N2.F1.20.1 19 snubber to perform its function or provide support.

Snubber 2-SI-HSS-421.02 CR442784, missing spacer on piston rod clevis pin, verified F-Al FI.IOD that missing spacer does not impact ability of snubber to

  1. N2.11.10.095 perform its function or provide Summary# Nsupport.

Snubber 2-RH-HSS-102 CR443946, loose bolt on pipe clamp, low fluid, tested SAT, F-A/ Fl.20D no slipping, evaluated as functional. Performed Summary # N2.F1 .20.371 additional examinations -

ST SAT.

Attachment Weld 12H *CR444219, Relevant indication found. CC N-586-1 B-KI B10.20 evaluation, construction flaw Summary # N2.B10.20.001 at surface. Ground out, teedST tested SAT.

Snubber 2-RC-HSS-459.01 CR444443, snubber & pipe F-A /FI. 1OD clamp alignment/binding, Summary # N2.F1.10.222 tested SAT RPVH Pens #8, 15, and 23 CR443870, discoloration and B-E / B4.30 staining, cleaned and found no degradation. Evaluated Summary # N2.B4.30.001 SAT.

RPVH Pen #18 CR444072, canopy seal weld B-E / B4.30 leakage from above, boric Summary # N2.134.30.001 acid residue, no degradation RPVH Pen #41 CR444091, residue from B-E I B4.30 canopy seal identified at pen Form No. 729595 (Aug 2009)

Form OAR-I, Owner's Activity Report Dftminion- ERAA-S-0 ATTACMN I ae3o Summary# N2.B4.30.001 #18, no degradation Spring Hanger SH-1 CR446060, owner elected F-A / FI. 1OC examination found loose nut, evaluated as able to perform Summary# N2.Fl.10.263 design function Restraint R-537 CR444413, PSI found F-A / F1.20B clearance issue, evaluation determined within the Summary # N2.F1.20.253 standard.

CR448737, rub marks and no Reactor Vessel Pad Support-5 measurable gap on one side.

No depth or displaced metal, F-A I F1.40B free to move, permits thermal growth and restrains in lateral Summary # N2.F1 .40.067 and vertical direction, meets function.

Form No. 729595 (Aug 2009)

Form OAR-I, Owner's Activity Report WDominion-Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Date Repair/Replacement Class Item Description Description of Work Completed Plan Number Snubber, 2-RC- 2nd preservice found 1 HSS-455.012preicfon 1 welded lug to anchor 2011-110 F-A / for paddle pin bent 11/6/2011 2011-120 F1.10D Summary# downward, N2.Fl.10.486 CR442774.

2"-WS-485-164-Q3 Replace 2" piping due 11/17/2011 2011-172 D-B / D2.10 downstream of 2- to MIC leak at weld SW-212 Form No. 729595 (Aug 2009)