ML12097A200

License Amendment Request to Revise Snubber Surveillance Requirements

ML12097A200
Person / Time
Site:	Millstone
Issue date:	04/02/2012
From:	Price J Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
12-036
Download: ML12097A200 (70)

Text

Dominion Nuclear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 'i Dominion Web Address: www.dom.com April 2, 2012 U.S. Nuclear Regulatory Commission Serial No 12-036 Attention: Document Control Desk NSSL/MLC RO Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3 LICENSE AMENDMENT REQUEST TO REVISE SNUBBER SURVEILLANCE REQUIREMENTS In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) is submitting a license amendment request to revise Technical Specification (TS) 3/4.7.10, "Snubbers," for Millstone Power Station Unit 3 (MPS3). The proposed change would revise the TS surveillance requirements for snubbers to conform to the MPS3 Snubber Examination, Testing, and Service Life Monitoring Program Plan.

Attachment 1 to this letter describes the proposed changes. Attachment 2 provides the marked-up TS pages. Marked-up TS Bases pages are provided in Attachment 3 for information only. Attachment 4 contains a detailed comparison of the current surveillance requirements in TS 4.7.10 to the revised snubber program requirements and justification of the changes. Finally, a copy of the Snubber Examination, Testing, and Service Life Monitoring Program Plan is provided in Attachment 5.

The proposed amendment does not involve a Significant Hazards Consideration under the standards set forth in 10 CFR 50.92. The Facility Safety Review Committee has reviewed and concurred with the determinations herein.

Issuance of this amendment is requested by April 2, 2013, with the amendment to be implemented within 30 days.

In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the State of Connecticut.

Serial No: 12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Page 2 of 3 Should you have any questions in regard to this submittal, please contact Ms.

Wanda Craft at (804) 273-4687.

Sincerely, J.eaPrice Vi e P esident - Nuclear Engineering COMMONWEALTH OF VIRGINIA COUNTY OF HENRICO The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by J. Alan Price, who is Vice President - Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before me that he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this 17 day of 4&,eyi ,2012.

My Commission Expires:

_ ONotary .bi Attachments:

1. Evaluation of Proposed License Amendment

2. Marked-Up Technical Specification Pages

3. Marked-Up Technical Specification Bases Pages

4. Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements

5. U3-24-IST-SNUB-BAP01, Snubber Examination, Testing, and Service Life Monitoring Program Plan Commitments made in this letter:

DNC commits to revise the MPS3 Inservice Inspection program to include the inspection requirements of the 2004 Edition (no Addenda) of ASME BPV Code, Section Xl, Article IWF-5300(c) for integral and non-integral snubber attachments by the start of the next refueling outage (i.e., 3R15).

Serial No: 12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Page 3 of 3 cc: U.S. Nuclear Regulatory Commission Region I Regional Administrator 475 Allendale Road King of Prussia, PA 19406-1415 C. J. Sanders NRC Project Manager U.S. Nuclear Regulatory Commission, Mail Stop 08B3

.One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Bureau of Air Management Monitoring and Radiation Division Department of Environmental Protection 79 Elm Street Hartford, CT 06106-5127

Serial No.12-036 Docket No. 50-423 ATTACHMENT I EVALUATION OF PROPOSED LICENSE AMENDMENT DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 1 of 8 EVALUATION OF PROPOSED LICENSE AMENDMENT

1.0 INTRODUCTION

In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) is submitting a license amendment request to revise Technical Specification (TS) 3/4.7.10, "Snubbers," for Millstone Power Station Unit 3 (MPS3). The proposed change would revise the TS surveillance requirements for snubbers to conform to the MPS3 Snubber Examination, Testing, and Service Life Monitoring Program Plan.

2.0 PROPOSED CHANGE

S The proposed changes to the MPS3 TSs are summarized below:

• Reference to Specification 4.7.10g. in TS ACTION 3.7.10 would be replaced with reference to Specification 4.7.10.

0 TS Surveillance Requirement (SR) 4.7.10 would be revised to replace specific surveillance requirements for demonstrating snubber operability with reference to the "Snubber Examination, Testing, and Service Life Monitoring Program Plan."

0 Section 6.8.i, "Snubber Testing Program," would be added to the Administrative Controls Section 6.8, Procedures and Programs, of the TSs to provide a description of the snubber testing program.

A mark-up of the proposed TS pages is provided in Attachment 2. A comparison of the current TS 4.7.10 surveillance requirements to the revised MPS3 snubber program requirements and justification of the changes is provided in Attachment 4.

3.0 BACKGROUND

At MPS3, snubber visual inspection and functional testing are performed in accordance with the specific requirements of TS 3/4.7.10. As requested by DNC in Relief Request IR-3-01, the NRC authorized use of TS 3/4.7.10 (Reference 8.2) for the third 10-year inservice inspection (ISI) interval in lieu of the requirements contained in the 2004 Edition (no Addenda) of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code,Section XI, Articles IWF-5300(a), 5300(b) and 5300(c)

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 2 of 8 (Note: DNC did not seek relief from the requirements of IWF-5200(a), 5200(b) and 5200(c)). MPS3's third 10-year ISI interval began on April 23, 2009 (Reference 8.1).

10 CFR 50.55a(g)(4)(ii) requires that inservice examination of components conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) 12 months before the start of the 120-month inspection interval. If a revised ISI program for a facility conflicts with the TSs for the facility, 10 CFR 50.55a(g)(5)(ii) requires licensees to apply to the Commission for amendment of the TSs to conform the TSs to the revised program.

For the remainder of the third 10-year interval, as permitted by 10 CFR 50.55a(b)(3)(v),

DNC intends to adopt Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants," of the ASME OM Code, 2004 Edition (no Addenda), in place of the requirements for snubbers in Section XI, Articles IWF-5200(a) and (b) and IWF-5300(a) and (b). 10 CFR 50.55a(b)(3)(v) also requires that when using this permitted alternative, preservice and inservice examination of snubbers must be performed using the VT-3 method specified in IWA-2213. As such, the proposed changes to TS 3/4.7.10 are required to conform the TSs to the revised snubber program.

As identified above, Relief Request IR-3-01 granted relief from the requirements of the 2004 Edition (no Addenda) of ASME BPV Code, Section Xl, Articles IWF-5300(a),

5300(b) and 5300(c) for the third 10-year ISI interval since the use of TS 3/4.7.10 provided an acceptable level of quality and safety. With the adoption of ISTD, the requirements of Articles IWF-5200(a) and (b) and IWF-5300(a) and (b) will be met for snubbers.

DNC commits to revise the MPS3 ISI program to include the inspection requirements of the 2004 Edition (no Addenda) of ASME BPV Code, Section Xl, Article IWF-5300(c) for integral and non-integral snubber attachments by the start of the next refueling outage (i.e., 3R15). DNC will continue to meet the requirements of IWF-5200(c).

Following approval of this license amendment request and fulfillment of the commitment contained herein, Relief Request IR-3-01 will no longer be needed.

4.0 TECHNICAL ANALYSIS

Licensees are required to perform the inspection and testing of snubbers in accordance with ASME BPV Code, Section Xl or the OM Code and the applicable addenda as required by 10 CFR 50.55a(g) or 10 CFR 50.55a(b)(3)(v), except where the NRC has granted specific written relief pursuant to 10 CFR 50.55a(g)(6)(i), or authorized alternatives pursuant to 10 CFR 50.55a(a)(3). 10 CFR 50.55a(a)(3) states that licensees may use alternatives to the requirements of 10 CFR 50.55a(g) when

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 3 of 8 authorized by the NRC if (i) the proposed alternatives would provide an acceptable level of quality and safety, or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

As noted in Regulatory Issue Summary 2010-06 (Reference 8.3), licensees have the option to control the ASME Code-required ISI and testing of snubbers through their TSs. For plants using their TSs to govern ISI and testing of snubbers, 10 CFR 50.55a(g)(5)(ii) requires that if a revised ISI program for a facility conflicts with the TSs, the licensee shall apply to the Commission for amendment of the TSs to conform the TSs to the revised program. Therefore, when performing 120-month program updates in accordance with 10 CFR 50.55a(g)(4), licensees must submit any required amendments to ensure their TSs remain consistent with the new code of record or NRC-approved alternative used in lieu of the code requirements. The TSs governing the snubber ISI and testing program do not eliminate the 10 CFR 50.55a requirements to update the program at 120-month intervals, in accordance with 10 CFR 50.55a(g)(4), or to request and receive NRC authorization for alternatives to the code requirements, when appropriate.

The proposed change replaces the specific TS requirements for snubber examination, testing and service life monitoring with reference to the program for examination, testing and service life monitoring for snubbers, thereby ensuring the TSs are consistent with the revised snubber program.

Snubbers will continue to be demonstrated operable by performance of a program for examination, testing and service life monitoring in compliance with 10 CFR 50.55a or authorized alternatives. The proposed change to TS ACTION 3.7.10 for inoperable snubbers is administrative in nature and is required for consistency with the proposed change to TS SR 4.7.10. The program for inspection and testing of snubbers in accordance with ASME BPV Code, Section Xl or the OM Code and the applicable addenda as required by 10 CFR 50.55a(g) is required to include evaluation of supported components/systems when snubbers are found to be unacceptable.

5.0 REGULATORY ANALYSIS

5.1 No Significant Hazards Consideration The NRC has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c). A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with a proposed amendment would not: 1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or 2) Create the possibility of a new or different kind of accident from any

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 4 of 8 accident previously evaluated; or 3) Involve a significant reduction in a margin of safety. DNC has evaluated whether or not a significant hazards consideration (SHC) is involved with the proposed change. A discussion of these standards as they relate to this change request is provided below.

Criterion 1 Will operation of the facility in accordance with the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

The proposed changes revise TS SR 4.7.10 to conform the TSs to the revised snubber program. Snubber examination, testing and service life monitoring will continue to meet the requirements of 10 CFR 50.55a(g) except where the NRC has granted specific written relief, pursuant to 10 CFR 50.55a(g)(6)(i), or authorized alternatives pursuant to 10 CFR 50.55a(a)(3).

Snubber examination, testing and service life monitoring is not an initiator of any accident previously evaluated. Therefore, the probability of an accident previously evaluated is not significantly increased.

Snubbers will continue to be demonstrated operable by performance of a program for examination, testing and service life monitoring in compliance with 10 CFR 50.55a or authorized alternatives. The proposed change to TS ACTION 3.7.10 for inoperable snubbers is administrative in nature and is required for consistency with the proposed change to TS SR 4.7.10. Therefore, the proposed changes do not adversely affect plant operations, design functions or analyses that verify the capability of systems, structures, and components to perform their design functions. The consequences of accidents previously evaluated are not significantly increased.

Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

Criterion 2 Will operation of the facility in accordance with this proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed changes do not involve any physical alteration of plant equipment. The proposed changes do not change the method by which any safety-related system

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 5 of 8 performs its function. As such, no new or different types of equipment will be installed, and the basic operation of installed equipment is unchanged. The methods governing plant operation and testing remain consistent with current safety analysis assumptions.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.

Criterion 3 Will operation of the facility in accordance with this proposed change involve a significant reduction in the margin of safety?

Response: No.

The proposed changes ensure snubber examination, testing and service life monitoring will continue to meet the requirements of 10 CFR 50.55a(g) except where the NRC has granted specific written relief, pursuant to 10 CFR 50.55a(g)(6)(i), or authorized alternatives pursuant to 10 CFR 50.55a(a)(3). Snubbers will continue to be demonstrated operable by performance of a program for examination, testing and service life monitoring in compliance with 10 CFR 50.55a or authorized alternatives.

The proposed change to TS ACTION 3.7.10 for inoperable snubbers is administrative in nature and is required for consistency with the proposed change to TS SR 4.7.10.

Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Conclusion Based on the above, DNC concludes that the proposed changes do not represent a significant hazards consideration under the standards set forth in 10 CFR 50.92(c).

5.2 Applicable Regulatory Requirements/Criteria 10 CFR 50.55a(g)(4)(ii) requires that inservice examination of components conducted during successive 120-month inspection intervals must comply with the requirements of the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) 12 months before the start of the 120-month inspection interval.

If a revised snubber program for a facility conflicts with the TSs for the facility, 10 CFR 50.55a(g)(5)(ii) requires licensees to apply to the Commission for amendment of the TSs to conform the TSs to the revised snubber program.

The proposed change amends the TS surveillance requirements to conform the TS to the revised snubber program which shall meet the requirements of 10 CFR 50.55a(g)

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 6 of 8 except where the NRC has granted specific written relief, pursuant to 10 CFR 50.55a(g)(6)(i), or authorized alternatives pursuant to 10 CFR 50.55a(a)(3).

In conclusion, based on the considerations discussed above, (1-) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 ENVIRONMENTAL CONSIDERATION

DNC has determined that the proposed amendment would change requirements with respect to installation or use of a facility component located within the restricted area, as defined by 10 CFR 20, or an inspection or surveillance requirement. DNC has evaluated the proposed amendment and has determined that it does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released off site, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need to be prepared in connection with the proposed amendment.

7.0 PRECEDENTS The changes to TS 3/4.7.10 are similar to changes submitted by Public Service Electric and Gas (PSEG) Nuclear, LLC for Salem Generating Station, Units 1 and 2, and by DNC for Millstone Power Station Unit 2 (MPS2). The applicable references for these changes are provided below:

7.1 PSEG Letter LR-N10-0363, License Amendment Request: Changes to Snubber Surveillance Requirements [for Salem Units 1/2], dated October 4, 2010 (Accession No. ML102780066).

7.2 PSEG Letter LR-N11-0107, Response to Draft Request for Additional Information - License Amendment Request: Changes to Snubber Surveillance Requirements [for Salem Units 1/2], dated April 7, 2011 (Accession No. ML110980107).

7.3 PSEG Letter LR-N 11-0151, Response to Draft Request for Additional Information - License Amendment Request: Changes to Snubber

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 7 of 8 Surveillance Requirements [for Salem Units 1/2], dated May 23, 2011 (Accession No. ML111430636).

7.4 NRC Letter dated August 25, 2011, Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendments Re: Technical Specification Requirements for Snubbers (TAC Nos. ME4796 and ME4797).

7.5 DNC Letter 11-354, Millstone Power Station Unit 2, License Amendment Request to Revise Snubber Surveillance Requirements, dated September 21,2011.

The following differences were noted between DNC's license amendment request for MPS3 and the requests submitted for Salem Units 1/2 and MPS2:

" MPS3 TSs include surveillance requirement 4.7.1Oa., "Inspection Types."

This requirement is not contained in the Salem Units 1/2 TSs but is contained in the MPS2 TSs.

• The following surveillance requirements are not included in the Salem Units 1/2 TSs or in the MPS2 TSs.

1) TS 4.7.1Od., "Transient Event Inspection"

2) The representative sample plan described in TS 4.7.10e.2

2) The 55 Plan described in TS 4.7.1Oe.3

3) A requirement to retest snubbers (i.e., TS 4.7.1Oe.) upon failure of test equipment during functional testing

4) TS 4.7.10h., "Functional Testing of Repaired and Replaced Snubbers"

" In accordance with MPS3 TS 4.7.1 0e. 1, for each snubber that does not meet the test acceptance criteria, an additional 5% of that type of snubber shall be functionally tested. This requirement is the same for MPS2. For Salem Units 1/2 TS 4.7.9.c, an additional 10% is required.

As noted in Attachment 4 of this submittal, the revised snubber program requirement for testing failures of MPS3 snubbers is equivalent to those of the current TS.

0 For Salem Units 1/2, TS 4.7.9.c requires retest during the next test period of failed snubbers that are repaired and installed in another position.

MPS3 TS 4.7.1Oe. and MPS2 TS 4.7.8.d do not contain this requirement nor is it required by ISTD-5500.

Serial No.12-036 Docket No. 50-423 Revision to TS 3/4.7.10, Snubbers Attachment 1, Page 8 of 8

8.0 REFERENCES

8.1 Millstone Power Station Unit 3, Third 10-Year Interval Inservice Inspection Program and Associated Proposed Alternatives and Relief Requests, April 28, 2009 (Accession No. ML091310666).

8.2 Millstone Power Station, Unit No. 3, Issuance of Relief Request IR-3-01 Regarding Use of American Society of Mechanical Engineering Code, Section Xl, Appendix VIII (TAC No. ME1254), dated April 6, 2010 (Accession No. ML100680118).

8.3 NRC Regulatory Issue Summary 2010-06, "Inservice Inspection and Testing Requirements of Dynamic Restraints (Snubbers)," June 1, 2010 (Accession No. ML101310338).

Serial No.12-036 Docket No. 50-423 ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATION PAGES DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

PLANT SYSTEMS 3/4.7.10 SNUBBERS LIMITING CONDITION FOR OPERATION 3.7.10 All snubbers shall be OPERABLE. The only snubbers excluded from the requirements are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.

APPLICABILITY: MODES 1, 2, 3, and 4. MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES.

ACTION:

With one or more snubbers inoperable on any system, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable snubber(s) to OPERABLE status and perform an engineering evaluation per Specification 4.7.10g. on the attached component or declare the attached system inoperable and follow the appropriate ACTION statement for that system.

Snubber Examination, Testing, and Service Life Monitoring Program Plan SURVEILLANCE REQUIREMENTS 4.7.10 Each snubber shall be demonstrated OPERABLE by performance of the au.gmented inser-i ce i.spection programt and th. ruir.m.nts of the inser.iee Inspe.tion 8rgrt" A9 u..ed in this speifiea+ti.. , "type of snubber"

.nu.bbers shall mean f.the sane design and mianufactturer-, iffespeetive of capacify.

Snubber-s are categorized as inaccessible or-accessible dur-ing raeater operation.

Eaeh of these categor-ies (inaecessible and accessible) mnay be inspeeted independently a.cording to the schedule determinted by T;able 1.7 2. The visu--l inspectiont intenval for-eaeh "ype of snubber- shalil be determined based upon the er-iter-ia provided in Table 1.7 2.

Visual: ...... " ie A . ee i*t-kl ee Gr-"=7 Visual inspections shall verify that (I) thie snubber.has no visible indications ei damage or-impair-ed OPERAB!1LIT-* (2) attaehments to the foundation or suppoffing strueturfe are funetional, and (3) fasteners for-the attachmenlt ofte snutbber to the component anid to the snubber-anchor-age are funtioeinal. Snubber-s which s- . . appa ...-- inprbe

• espeIe as a result.

T TTvofvisual inspections- shall

[l~ .4.^.-.-+ L.- -..be classifieda

.I.;. .

thle nlext visua--Fl inspection inteerv.al, provided thatt (1) the cautse of the rejection is clearly established and remedied for that pattietuler snubber and for other-snubberS MILLSTONE - UNIT 3 3/47-22 Amendment No. 32, 6-2, 74,-2--

Juiy 24, """2-PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) type that may be gener-ically suseeptible; and (2) the affcted snubber- is functionially tested in the as found condition and dctefmined OPERABLE; per SpecifiOatOn 1.7.1 O4f All ~ubr cn oncc oa nprbccmo hydaulc fuidrc~r~'irshall be coutiatd as unaccceptable fcr-determining the ncxt np-tccen tmormaf. A rcvicw and evaiuatt, n nall c perforefrnca and .a.um.nt..

to justib' eontinued eperatian with an unaaccoptable gaubber. If continucd eperatien cannat be justified, +he gnubber shail be deelar-ed inepcratble and th ACTION requirements shall be met-.

THIS PAGE INTENTIONALLY ~Ait inspeetion ghall be pcrf4crmed of all snubbers attached to seefieons of systems LEFT BLANK thlat havo .pr.n i unxpeeted, potentially damaging tranaients as deteriincd fram a review of operational data and a vistial inspeection of +he systems withint 6 mnonths fellowirng such an evcnt. in addition to sfttbisfig the -visual iftspeetion acccptancc critcr-ia, frccdom of motiont of mechanical sinubber-9 shall bo ver-ifiod uiging at least one of the following: (1) manually induccd snubber moivcmot; or (2) evalutation of int placc saubbeir piston. seoing;, or (3) stoking the ffcchaflical snubber through its full range of tr-avcl.

• . Functional Tests During the first refticling shutdown and at lca~t oncc per-21 moneths thcreaftcr-,*a rcepr-esentative sample of snubber-s of cach type shall bo tested using one of thc following sample plans. The sample plant fer cach ttypc shall be seleeted prior-to the test period and cannot+be changd dur-ing the test period. The NRC Regional Admittistfator- shall be notfified int writing of the sample plan sclcctcd for-caeh gntibber-type prior-to the test pcriod or the sample plan used in +hepr-ior-test pcriod shall be implcm..tcd:

4At l.t.. 10% of+he t*ota of each b1pe. of nubb.r shall be fu.nctionaly*

+ested eithor-in plaee or int a bench feut. For cach snubber of at +Ypo tha does not me t . .t ,*te +,anal+es+at*et t criteria ot Sp-eifit*+ion1.7.1 Of., an additional I5% . of .bber that.hal.

Vfp1 of bo ftinon*a*Jlly tst. d until no m*,r, fail-res arc found or until all subber, of that typo have been futnctionally +egcd;,or Excpt....

the :nbber. rld to fu-ancior.

may be dcferrcd until the end ofthe newt roftclintg outage or- e 1ia: than Septemb*r- 10, 1999,*

whihever-is earlier-.

MILLSTONE - UNIT 3 3/4 7-23 Amendment No. 6-2, 7, 4-00, 4-. 67 Th

Apilt 7, t9 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

e. Fu.n.t.onal l.es.t (Continued) 2ý A representaive satmple of eaceh type of snubber shall be fuhefitionih tested in accoardance vwith Figure 1.7 1. "C" is the total! nutmber of snubbers of a type foeund not meeting the acceptancee requir-ements ot Specifeeation 4.7.1 Of. The cumutlative number of s9nubbers9 of a type tested is denoted by "N". Test results shall be plotted sequenttially int the order ot

{

sample assignmnent (i.e. eaceh snubber shall be plofted by its assigned order in the random sample, ntta by the order of testing). if at any time the poin plofted falls in the "Accept" region, testing of snubbers of thart type may be teninaed.When the point ploffed lies in the "Continue Testing" region, additional snubbers9 of that type shall be tested uintil the pointt falls int the "Aeept region or th "ej eet"region,or all th nbe- ftha pe THIS PAGE have been tested;, or.

INTENTIONALLY LEFT BLANK A~n initial representative sample of 55 snubbers shall be functionally test d.

-3)

For-each snubber t-ype whieh does not meet the functiontal test aeceptam criteria, another sample of at least one half the size of the iritial sample shall be tested until the total number tested is equal to the intitial sample siz!e multiplied by the factor, 1 C/G2, where "C=" is the number of snutbb 9 found which do not mneet the functional test aeceptancee criteriat. The rest S from this sample plan shalil be ploffed using ant Aeeept" linte wnh follows the equation N - 55(1 i Cý2). Each snubber point shoiuld b plotted asg soon as the snubber is tested. if the point ploffed falls on or below the "Aeeept" line, testing of that type of snubber my be t nat ed if the po*int plofed fIalls above the "Accept" linte, testin.g must con-tinue unftil the point+falls in the "Aeeept" region or all thte snubbers9 of that typ have been tested.

T;esting equipment failure during funefitioal testing may invalidate that daty':s testing and allow that day's testing to resume anew at a later timne provided all snubbers tested with the failed equipment dur-ing the day of equipment failutre are r-etested. The representai-ve sample selected for the funcetional test samploe plants shall be randomly, seleetcd fromt the snubbers of each type and reviewed before beginning the testing. The r-eview shall ensure, as far-us pr-acticable, that they are re@pr-esentative of the var-ious configurations, operating en-vironenfifts, reange ot size, and capacity of snubb..rs..of each type... ubber.s placed in the same loc.aion as snubbers. which failed the pr.evious functional test shall be retested at the time o the next functional test but shall not be incluided int the sample plan. if dur-ing the func~itioal testinig, additional samfpling is required due to failure of ontly onte type of sn.bber., the functional test reslts shall be rneviewed at that time to deterie i additional samples shoulid be limited to the type of snubber which has failed thwe fitnefianal es~ing MILLSTONE - UNIT 3 3/4 7-24 Amendment No. i-& ýý

Jauaily 31, 1986 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

f. Punetional Test ikeeestanee Gr-itepm

• "1*1 1- - *'* *? 1 -I_-11 ..... :*__ *I_

Thne snubbsor fiu unetaiR testL shall ver-ify that:.

Aetivmatjn (r-estraining atteion) is ahieved withint the speeified rnoi both tcnFion enecmpr-esieft; Snubber- bleed, of felease r-ato where r-eguir-ed, is present in both tettsion and eampr-esion, within the speeified range;

ký

3) Far-meehanicali gnubbers, the foree required two i".4itiae or maintait motion of the snubber- is withint +hespeeified range int both dircctions of travel; and, For-sfntbber-9 speeifieally requiroed not to displaee uinder eamfntinots lead, THIS PAGE dth afbility of the snubber to withstand load withaou displaeemfent.

INTENTIONALLY LEFT BLANK Testittg mcethads may be used to measure pearamnetcr9 indireetly or, parameterg other than the e speeified if these resulfs can be coprelatod to the speeified parameters through established methods.

Aft enginecr-ing cvalumtion shall bý made of, cach feilurc to meet +hefuncetional toet acceeptancee cariterfi-a to dcoin he eftuge of th fa~ilulre. The r-estlts cfth evaluation shall be used, if applieabic, in seleefing snubber-s to be te~tedina e&-o4 to d.te....-in 4A-th OP .. .RAB IL.T. of other so h-h-A 1-i...

rp 4tive of +'p-which may be subjeet to the game feiluir- mode-For the satubber- found inoper-ablo anPgneing evaluation shall be per-ffmend ont the compontentg to whicah thea inqoper-able smubber-s atrc ffaachd. The puorps at dthb engineering evalumatio shall be to determine if the components to which the inoeperable snubbers are a~fached were advergely ftfetetd by the ittapefrabiliy oa the .nubber. int or-der to .nt*ure that..the mp..*+1t- remain

.. apable of mee1tig the if anty snubber gceleted for-ffitntional +etiftig either failg to lock up or-failst mvie., fro5!en in plaee, the eauise will lbý evalutied and, if caused by manfactutrer or design deficieney, all snubbers of the samfe &+esujctt he sante defect shall be funtmeionally tested. This tcg~ting requiroemenlt slhall independent of the requirements staed in Specificationt 4.7.l1 g. for snuebbeors not meeting +he fudnctional test acceptanee cr-itoria.

MILLSTONE - UNIT 3 3/4 7-25

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

h. punetionai testifte of tfsenair-ea ana iecewaeeo-b"unner-s Stnubbe-rs whieh fail the visual ingpectian or tho func*tin*al test aoeeptancc criteria shall be repaired atr roplaeed. Replaeoment snubbers and snutbbers which have rcarvhich mfight afFeet the futnetional test resuilts shall be tested to meet the funcý-tionlal tcst eritoria bef-arc installation in the unit. Mechanieal snubbers shall have met the aecoptanco ntr-iteio subsequent to their mast racant se~iee, atnd the freeadom of-motion test must have been perfermed within 1-2 moinths beffore being insta*flld in the unit.

f.

The sefyiee lifc of hydrautlic and mcchanical snubbers shall be moenitor-ed to ensure that the sor.'ico life is not eiieooded between s "r--eillanoo.

inspctn. Tho maximm eiepeeted sepviee life for-variouis seals, springs, and at-her cr-itical pafts shall bo detenmined and Rqtabliwhed based ont eniorn ifcnnaion and shall be

-A---ro an~ tuositw itsery iau art" .. hall of r.,p÷la d .. tat.. ton il maximum scriee life W~ill net be elfeedo

... 4 .......

during a p io.dwh enth esnubb.. is rogquirod to ho OPERAB~LE. T~ho parts replacamntes shall be daeumcnte dand +he docutmontiati shalil ho retained int acoordanco with Quality Assurar icc ;roaratm +orietai Kcort.-

ITHIS PAGE INTENTIONALLY LEFT BLANK I MILLSTONE - UNIT 3 3/4 7-26 Amendment No. t7t-Z;7

dnnuary r4-995-T-"6F4.E-74 SNU1BBER VISUAL INSPECTION INTEVAL NIJM-RFI1 OFrr gZIN TTfl T rP 0444"pFRRZ peptilmion orf ttaegary E*xtend int*ra l Rcepem ne4eea Roeduco Intcra (aeseee4-atd-4) Eiefeg-3-aftd-6) (aeiee4 afld-6) (4e4oes4ftvrd-6) 4-W0 0 4-4 440 0 44 400 2 --

400 8 4-8 436

-00 4-2 24 48

.4.. 20 40 49 1 0arge-2.9 -56 4-09 Note 1: zr iilr~~tenp 9zt2mr'i~II Ai li vv 1 v p iais a c 2 THIS PAGE 'l%'vtlllij L Aa tLJ'JA ev 1... p 'flA~iL. .qm1m~l* b-,tlLU*.J 't...JL INTENTIONALLY basedpothoi a sibit during powor oporation asacsible or :nreacossiblc.

LEFT BLANK T-hoccatogor-ics may bEcoamninod sepatreatly or joinitly. However, thaliccnisccmutst make T- -- --+and I. docuiment

• - L. .. . that. dccision

. . . .. 1 ." .. before

. . ÷ . any . . inspcction

. . . .4 + and

. . .shiall

. I.

• uisc "that decision

. . . ÷ .1 as thc basis.pon.which to dct.inc ... thcn i.....nsctin

.... .... in..tc.al fr that ca . .tcgo..

Noe e2!

A, B, or-C if that integcr- includcd a fractionial valuce of unacccptablc snlubbcrs a dctcincd by initcfolaiofn.

if thc numbcr- of uinacccptablc snutbbcr-s is cgual to or-lcss than thc numfbcr-int Columfn A, the rrta inisncction intcn'al b t'icc thc r-rcvious inton-al but+ i g~catcr lw hoa 1k8II may no tha if +th numb.. of una...ptable snubbcrs is cg.l to or losh +than

.thnumbr in Colu.mn B buti groator-than i~athonubor- in Column A, thc ncxt inspootion intcn'al shalil bo thce Nate 4! samo as the prvious intcn'al.

If tho numb.. of.^unacc... optal snubb. r is,_  : .ua.. to or gr ,.at^r than* th. number in Columfn C, tho cx inpotion intcn'al shall boa two thrd f the prceviouts intoreal.

How.v.r, if th numb- . of unac..I.ptabl snubbrs is loss +hant thc number in Coiu.n C but.+ gratnr-than tho numbo- io B, tho n-xt i.tc...s*+ hall be r-oduc4.d proportionally by intopolation, that is, the proviouts intcn'al!shalil be roducoed bya faco th*p At is one third of the r-atio of the difforonco between tho numbor ot uinacoopetabl snutbbors founfd during the provious inton-al and the numfbor in Column, n to"i Mc a, oronolec inl c nufmi r, inq .uIum10ANK n qý aM- .L.

MILLSTOb E - UNIT 3 3/4 7-27 Amendment No. 6-2,

junudry 5 t-995

-AB16E.4.-2 SNUBER ISUA INPEC-TiON iNTTER-L

• 1

• g Nate6-. 1:he wrcvisicns et s13eeffteftf8 4.0.2 are appiealgie fer-all t~ctisicetn intcrvais uo tc l

fifle faefutnam 4 0 ffieftt*sý ITHIS PAGE INTENTIONALLY LEFT BLANK MILLSTONE - UNIT 3 3/4 7-28 Amendment No. 6-2, 470

-anarmy 3, t 99 5 10 - I- I- I- I- I - I- I- I- I-I I I I I I I I I

-f

/

8 ----------

/

7 6

C5 4 UNATINUE TESNING 3

ýsssll 2

CCEPIT 1

S2030 405060 70 80 90 0 N

THIS PAGE INTENTIONALLY FGURý. 1.7-4 LEFT BLANK SAMPLEB PLAN 2) FOR SNUBBER FUNCTIONAL TEST4-MILLSTONE - UNIT 3 3/4 7-29 Amendment No. 4-6, +00-

IFor Information Only September 30, 2008 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) associated with a crack(s), then the indication need not be treated as a crack.

e. Provisions for monitoring operational primary to secondary LEAKAGE.

h. Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVs), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a. The definition of the CRE and the CRE boundary.

b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.

c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C. I and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

The following are exceptions to Sections C. 1 and C.2 of Regulatory Guide 1.197, Revision 0:

1. Appropriate application of ASTM E741 shall include the ability to take minor exceptions to the test methodology. These exceptions shall be documented in the test report, and

2. Vulnerability assessments for radiological, hazardous chemical and smoke, and emergency ventilation system testing were completed as documented in the UFSAR and other licensing basis documents. The exceptions to the Regulatory Guides (RG) referenced in RG 1.196 (i.e., RG 1.52, RG 1.78, and MILLSTONE - UNIT 3 6-17d Amendment No. 24-3, 245

September 30, 2008 ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

RG 1.183), which were considered in completing the vulnerability assessments, are documented in the UFSAR/current licensing basis. Compliance with these RGs is consistent with the current licensing basis as described in the UFSAR and other licensing basis documents.

d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREVs, operating at the flow rate required by the Surveillance Requirements, at a Frequency of 48 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

e. The quantitative limits on unfiltered air inleakage into the CRE.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

INSERT "A" The provisions of Surveillance Requirement 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c. and d., respectively.

6.8.5 Written procedures shall be established, implemented and maintained covering Section I.E, Radiological Environmental Monitoring, of the REMODCM.

6.8.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 6.8.5 above shall be reviewed by an individual (other than the author) from the organization responsible for the REMP and approved by appropriate supervision.

Temporary changes may be made provided the intent of the original procedure is not altered and the change is documented and reviewed by an individual (other than the author) from the organization responsible for the REMP, within 14 days of implementation.

MILLSTONE - UNIT 3 6-17e Amendment No.

INSERT"A"1 Snubber Testing Program This program conforms to the examination, testing and service life monitoring for dynamic restraints (snubbers) in accordance with 10 CFR50.55a inservice inspection (ISI) requirements for supports. The program shall be in accordance with the following:

a. This program shall meet 10 CFR 50.55a(g) ISI requirements for supports.

b. The program shall meet the requirements for ISI of supports set forth in subsequent editions of the Code of Record and addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code and the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code) that are incorporated by reference in 10 CFR 50.55a(b), subject to its limitations and modifications, and subject to Commission approval.

c. The program shall, as allowed by 10 CFR 50.55a(b)(3)(v), meet Subsection ISTA, "General Requirements" and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants" in lieu of Section Xl of the ASME BPV Code ISI requirements for snubbers, or meet authorized alternatives pursuant to 10 CFR 50.55a(a)(3).

d. The 120-month program updates shall be made in accordance with 10 CFR 50.55a (including 10 CFR 50.55a(b)(3)(v)) subject to the limitations and modifications listed therein.

Serial No.12-036 Docket No. 50-423 ATTACHMENT 3 MARKED-UP TECHNICAL SPECIFICATION BASES PAGES For Information Only DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

For Information Only . .CRMP3-025 05 .

Matreh*I 4, 2@06vv..

PLANT SYSTEMS BASES LCO 3.7.9 ACTION statement:

With one Auxiliary Building Filter System inoperable, restoration to OPERABLE status within 7 days is required.

The 7 days restoration time requirement is based on the following: The risk contribution is less for an inoperable Auxiliary Building Filter System, than for the charging pump or reactor plant component cooling water (RPCCW) systems, which have a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> restoration time requirement. The Auxiliary Building Filter System is not a direct support system for the charging pumps or RPCCW pumps. Because the pump area is a common area, and as long as the other train of the Auxiliary Building Filter System remains OPERABLE, the 7 day restoration time limit is acceptable based on the low probability of a DBA occurring during the time period and the ability of the remaining train to provide the required capability. A concurrent failure of both trains would require entry into LCO 3.0.3 due to the loss of functional capability. The Auxiliary Building Filter System does support the Supplementary Leak Collection and Release System (SLCRS) and the LCO ACTION statement time of 7 days is consistent with that specified for SLCRS (See LCO 3.6.6.1).

Any time the OPERABILITY of a HEPA filter or charcoal adsorber housing has been affected by repair, maintenance, modification, or replacement activity, post maintenance testing in accordance with SR 4.0.1 is required to demonstrate OPERABILITY.

Surveillance Requirement 4.7.9.c Surveillance requirement 4.7.9.c requires that after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation a charcoal sample must be taken and the sample must be analyzed within 31 days after removal.

The 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation requirement originates from Regulatory Guide 1.52, Revision 2, March 1978, Table 2, Note "c", which states that "Testing should be performed (1) initially, (2) at least once per 18 months thereafter for systems maintained in a standby status or after 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operations, and (3) following painting, fire, or chemical release in any ventilation zone communicating with the system." This testing ensures that the charcoal adsorbency capacity has not degraded below acceptable limits as wellas providing trending data. The 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> figure is an arbitrary number which is equivalent to a 30 day period. This criteria is directed to filter systems that are normally in operation and also provide emergency air cleaning functions in the event of a Design Basis Accident. The applicable filter units are not normally in operation and sample canisters are typically removed due to the 18 month criteria.

3/4.7.10 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. For the purpose of declaring the affected system OPERABLE with the inoperable snubber(s), an engineering evaluation may be performed, in accordance with Section 50.59 of 10 CFR Part 50.

Snubbtro are .las.ifi.dand grupd by design.. and ant.fi..t...r but nt by 9ize.

Stiubbers of the game martufaetur- but having different intcmal meehanbmis are elasified as diffcr-ent types. Far-eiample, meehanieal snubber-s utilizing the same design fcatur-es ofthe 2 kip, 10 heip and 100 lip efkpaci MILLSTONE - UNIT 3 B 3/4 7-23a Amendment No. 8-7, 4-1-9, 4-36, 4-4,

4te 3,32002 IFor Information Only PLANT SYSTEMS BASES 3/4.7.10 SNUBBERS (Continued) manuifacftured by Company "A" arc of the samc t-ype. Thc samne dcsign mcchanical snubbers manufacturced by Companty "B" for thc pufpeses of this Technical Specificoatin would bc ofa differcnt typc, as wouild hydrautlic snuibbers from cithcr manufacturcr.

A HAs of individual snubbcr-s with detailed inforafitfion of snubbcr location and sitc anfd ot systcmn affected shall bc available at the plant in accoardatnce with Section 50.741(c) of 10 CF-R Pan. 60. Thc acessibility of cach sn.ubber shall be determined and approved by the Plan Operations Revicw Committiee. The doetermination shall be batsed utpon the cxkisting r-adiation le-vcls and thc cxpected timc to pcr-form a visual inspcctiont int each snubber- location as well as other factors associatcd wvith accessibility during plant opcrations (c.g., tcmperaturce, atmospherc, location, etc.), and the rceeRMF .dations of Regulaory. Guides 8.8 and 8..10. The R-g:tN~n Ar deletion of any hydr-aulic or mnechanical snutbber-shall be made in accor-dancee with Sectiont 50.59 of 10CFR Pan 50.

The visual inspection frequency is based upon maintaining a constant level of snubber proetection to each safet r-elated system during an ead~hquakee or severe transient. Ther-efor-e, the required inspection inter~al var-ies inver-sely with the obsen'ed snubber failures on a givent system and is determined by the number-of inoaper-able snubbers9 found dluring an inspection of eac~h system. in order to establish the inspection frequency for each typ of snubberon a safet~y related system, it was assumed that the frequencey of sntubber failures and initiating events is cosant with time and that the failure of any snubber on that system could cautse the system to be untprotected and to result in failure during an assumfed initiating event. Inspecitios performed before that interval has elapsed may be used as at new referenmee point to determine the nex inspectio. .h .owever,the results of such early inspections perfoirmed befo.re the Original required time inmtcral has elapsed (nominal.time less 25%) may not+be used to lengthen the r-equi intspection interval. Any inspection whose results requireta shofter inispection inten'al wl oveaide the previous sehedule.

The acceptance criteria are to be used int the visual inispeetion to determine OPPERXBILITY: of the snubber-s. For exfample, if a fluid poft of a hydrautlic snubber is found to be uncovered, the snubber shall be declar-ed inoeper-able and shall not be determined OPERXBLE via To. provide assur.ance of snubb er-futfional reliability-, one of three f1unctinal testing metneas is usca wan tnc suaca accepwnee criteria:

4-: functionally test 10% of.a type of snubber with an additional tested for-each functsio-nal testing failure, or-

-2. Funetionalivestasnif ieadde-it apeae"ae rmjeintgn Functionally test a repr-esentaive sample size and determine sample acc.eptane or 1

ree~etion sinlg t ritnQ*tvla P'n~iir~v MILLSTONE - UNIT 3 B 3/4 7-24 Amendment No. 4-6, 8-7, +4-9, 6, "Revised by NRC letter A145:710"

613 L"R N". 10 9M3 010 JC.JJ.DI.U4t..ly* 6,v .20J-lJ 10.,l'a PLANT SYSTEMS IFor Information Only BASES 3/4.7.10 SNUBBERS (Continued)

Figurc 1.7 1 was dcx'lepcd using "Wald'. Sequential Pr.bability Rati. Plan" a, decr-ibed int "Quaiy Cntr... .. l and du.trialWn Sistic3" by A... J.Dunran.

P..man.nt or-ether... :mptions fr..m the... illame.. pr:"gr'am

. for individual snubbcrs may be granted by the Commbissin if a justifiable basis for-excmptien is pr-esented and, if appli.abl. , .nubb.rlife d..t.u.tiv. testing was pcf.d to qu.alifythnubb cr foerr&f th applicable design eenditions at either the eempiction of their-fabr-ication or-at a subsequent dato.

Snubbers so eixompted ghall be ligted int the list of inidiveidual-l snubber-9 indieating the eixtent of thc The scn'iee life of a gnubber. is estblighed via manufacturor input and infofrmatiefn thr-ough eensidefatien of the snubbc odifians ic.io and a~seeiatd installatieft and "taintcnancc reeards (newly insfelled snubbers, 3c01 rcplaccd, spring roplacod, in high radimatin ar-ea, int high temperature arca, ctc.). :Fhc rcequircmcnt to monitor the snabbef ser,'iee lifci iftcluded to engturc that the snubbers pcriadicalily tuIdcrgo pfmoatte a cyalutation in view af thcir age and apcrating eandifians. These feeards will provide sttatisfical bages fier fuftur eensideration of gfnubbcr sen'iee !if,--

3/4.7.11 DELETED 3/4.7.14 DELETED --r MILLSTONE - UNIT 3 B 3/4 7-25 Amendment Nos. -9,-84, 400, 44-9, 4-36,214

Serial No.12-036 Docket No. 50-423 ATTACHMENT 4 COMPARISON OF CURRENT TS SURVEILLANCE REQUIREMENTS TO REVISED SNUBBER PROGRAM REQUIREMENTS DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 1 of 12 Millstone Power Station Unit 3 (MPS3)

Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements Current'T'S Surveillance '* " equremnt.*:

Revised Snubber Program Justification JsiiainfrCagfor Cag Requiremnent 'Requirement.

4.7.10a. Inspection Types ISTD-5252 states that the total snubber At MPS3, snubbers are grouped into DTPGs population may be considered one Defined by design type in accordance with ISTD-5252.

As used in this specification, "type of snubber' Test Plan Group (DTPG), or alternatively, This snubber grouping is the same as that shall mean snubbers of the same design and differences in design, application, size, or type required by TS SR 4.7.10a.

manufacturer, irrespective of capacity. may be considered in establishing DTPGs.

See exception in ISTD-5253.

4.7.10b. Visual Inspections ISTD-4220(a) requires all snubbers to be Table ISTD-4252-1 is identical to TS Table considered one population for examination, or 4.7-2 for population/category sizes less than or Snubbers are categorized as inaccessible or alternatively, to categorize them individually as equal to 1000.

accessible during reactor operation. Each of accessible or inaccessible. The categories of these categories (inaccessible and accessible) accessible and inaccessible snubbers shall be Use of ISTD-4200 for snubber inservice may be inspected independently according to considered separately for examination, examination in lieu of current TS SR 4.7.1Oa.

the schedule determined by Table 4.7-2. The does not change the number of snubbers visual inspection interval for each type of ISTD-4220(b) requires the decision to examine required to be examined or the required snubber shall be determined based upon the the snubbers as one population or as separate examination intervals.

criteria provided in Table 4.7-2. categories to be made and documented before the scheduled examination begins and not Note 1 to TS Table 4.7-2 states that snubber changed during the examination.

categories may be examined separately or jointly. ISTD-4252(b) requires inservice examinations to be conducted in accordance with Table ISTD-4252-1.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 2 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Current TSSurveillance "ReVised Snubber Program- Justificatio for Change Requirement 'Requirement 4.7.1Oc. Visual Inspection Acceptance ISTD-4210 states that inservice examination shall 10 CFR 50.55a(b)(3)(v) allows the use of Criteria be a visual examination to identify physical subsection ISTD for inservice examination damage, leakage, corrosion, or degradation that requirements. Preservice and inservice Visual inspections shall verify that (1) the may have been caused by environmental exposure examinations are required to be performed snubber has no visible indications of or operating conditions; and external using the VT-3 visual examination method damage or impaired OPERABILITY, (2) characteristics that may indicate operational described in IWA-2213.

attachments to the foundation or supporting readiness of the snubber shall be examined.

structure are functional, and (3) fasteners The revised snubber program requirements ISTD-4231 requires that examinations shall include for the attachment of the snubber to the for inservice examination do not differ component and to the snubber anchorage observations for the following and the conditions significantly from the visual inspection are functional. shall be evaluated when found:

acceptance criteria in SR 4.7.10c.

(a) loose fasteners, or members that are corroded or deformed For integral and non-integral attachments, (b) disconnected components or other conditions the MPS3 ISI program will continue to meet that might interfere with the proper restraint of the inspection requirements of ASME movement Section Xl, Article IWF-5200(c). The ISI program will be revised to include the ISTD-4232 requires that examinations verify inspection requirements of IWF-5300(c). See snubbers do not restrain thermal movement to an Commitment.

extent that unacceptable stresses could develop in the snubber, the pipe, or other equipment that the snubber is designed to protect or restrain.

ISTD-4233 requires that examinations verify snubbers are shall be free of defects that may be generic to particular designs as may be detected by visual examination.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 3 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Current TS Surveillance; Re'vise'd Snubber .ProgramT Reurmn eurment Justification for Change 4.7.10c. (continued) ISTD-4240 permits snubbers classified as The revised snubber program requirements for unacceptable during inservice examination to evaluation and corrective action for inservice Snubbers which appear inoperable as a result be tested in accordance with the requirements examination are equivalent to those of current of visual inspections shall be classified as of ISTD-52 10. Results that satisfy the SR 4.7. Oc. for visual examination acceptance unacceptable and may be reclassified operational readiness test criteria of ISTD- criteria.

acceptable for the purpose of establishing the 5210 shall be used to accept the snubber, next visual inspection interval, provided that provided the test demonstrates that the (1) the cause of the rejection is clearly unacceptable condition did not affect established and remedied for that particular operational readiness.

snubber and for other snubbers irrespective of type that may be generically susceptible; and ISTD-4233 requires that fluid supply or content (2) the affected snubber is functionally tested for hydraulic snubbers shall be observed. If the in the as-found condition and determined fluid is less than the minimum amount, the OPERABLE per Specification 4.7.10.f. All installation shall be identified as unacceptable, snubbers found connected to an inoperable unless a test establishes that the performance common hydraulic fluid reservoir shall be of the snubber is within specified limits. Tests counted as unacceptable for determining the shall be performed in accordance with ISTD-next inspection interval. A review and 5210(b) and ISTD-5210(c). The initial test shall evaluation shall be performed and start with the piston at the as-found setting and documented to justify continued operation with be performed in the extension (tension) an unacceptable snubber. If continued direction, or in a mode that more closely operation cannot be justified, the snubber shall resembles the operating and design be declared inoperable and the ACTION requirements of the snubber.

requirements shall be met.

ISTD-4270 requires that snubbers that do not meet examination requirements of ISTD-4230 shall be evaluated to determine the root cause of the unacceptability.

ISTD-4280 requires that unacceptable snubbers shall be adjusted, repaired, modified, or replaced.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 4 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Current TS Surveilla'nce 'Revised SnubbeirProgram JsiiainfrCag Requirement Reurmn 4.7.10d. Transient Event Inspection ISTD-1750 requires if a transient dynamic The revised snubber program requirements for event occurs that may affect snubber evaluation and corrective action for a transient An inspection shall be performed of all operability, then the affected snubbers and dynamic event inspection are equivalent to SR snubbers attached to sections of systems that system shall be reviewed and appropriate 4.7.1Od.

have experienced unexpected, potentially corrective action taken. Any action so taken damaging transients as determined from a shall be considered independent of the review of operational data and a visual requirements-of ISTD-4100, -5100, -4200, inspection of the systems within 6 months -5200, -5300, -5400, and -5500.

following such an event. In addition to satisfying the visual inspection acceptance criteria, freedom-of-motion of mechanical snubbers shall be verified using at least one of the following: (1) manually induced snubber movement; or (2) evaluation of in-place snubber piston setting; or (3) stroking the mechanical snubber through its full range of travel.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 5 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Current TSSrveillance, ii~ qure.e"ht:,"!:::i.:il~:".ii eq ire Snubber Revise"d en ii~ii:*'iiii~i:ii~'*:iiiil Program.* .Justi.ficatiJu Justifiatio tiicaio :ffror ChangeaneChange::::

~Requirem~ent~ Requirement 4.7.10e. Functional Tests ISTD-5200 requires snubber operational The frequency of snubber testing in the readiness testing to be performed each fuel cycle, revised program is similar to the frequency During the first refueling shutdown and at Testing shall be performed during normal system specified in current TS SR 4.7.1Oe. The least once per 24 months thereafter, a operation, or during system or plant outages. readiness testing is performed every fuel representative sample of snubbers of each cycle which is approximately every 18 type shall be tested using one of the following ISTD-5240 states that snubber testing may begin months.

sample plans. The sample plan for each type no earlier than 60 days before a scheduled shall be selected prior to the test period and refueling outage.

cannot be changed during the test period.

ISTD-531 1(a) requires the initial sample to include ISTD does not contain a requirement to The NRC Regional Administrator shall be as practicable representation from the Defined notify the NRC regarding sample plan notified in writing of the sample plan selected Test Plan Group (DTPG) based on the significant selection prior to a specific test period.

for each snubber type prior to the test period features (i.e., the various designs, configurations, or the sample plan used in the prior, test operating environments, sizes, and capacities).

period shall be implemented:

4.7.10e. (continued) ISTD-5223 and ISTD-5224 permit snubbers to be The initial sample size in the revised tested in their installed location or in a bench test. program is as large as the size specified in

1) At least 10% of the total of each type of current TS SR 4.7.1 Oe.

snubber shall be functionally tested either in- ISTD-5261 requires snubbers of each DTPG to be place or in a bench test. For each snubber of tested using either: Per ISTD-5331, the mathematical expression a type that does not meet the functional test (a) the 10% testing sample plan for additional testing within the DTPG is acceptance criteria of Specification 4.7.10f., equivalent to the additional 5% testing an additional 5% of that type of snubber shall (b) the 37 testing sample plan expression contained in SR 4.7.10e.1.

be functionally tested until no more failures ISTD-5331 requires that testing shall satisfy the are found or until all snubbers of that type mathematical expressions as follows:

have been functionally tested; or (a) for each DTPG N > 0.1n + C(0.1n/2)

(b) for each failure mode group (FMG)

NF > CF(0.1n/2)

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 6 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

'CurrentTS Surveillance Revised'snu bber Program.iiiii , Justification Jui for Change i* ".:  !

Requirement Requirement 4.7.1Oe. (continued) ISTD-5261 requires snubbers of each Defined The 37 testing sample plan specified in ISTD-Test Plan Group (DTPG) to be tested using 5431 is equivalent to the sample plan

2) A representative sample of each type of either: contained in SR 4.7.1Oe.2.

snubber shall be functionally tested in accordance with Figure 4.7-1. "C" is the total (a) the 10% testing sample plan Specifically, the mathematical expression number of snubbers of a type found not contained in MPS3 TS Figure 4.7-1, C =

meeting the acceptance requirements of (b) the 37 testing sample plan 0.055N - 2.007, is the same as the Specification 4.7.1Of. The cumulative number expression, N = 36.49 + 18.18C, used in ISTD-of snubbers of a type tested is denoted by "N". For the 37 testing sample plan, ISTD-5431 5431.

Test results shall be plotted sequentially in the requires that testing shall satisfy the order of sample assignment (i.e. each snubber mathematical expressions as follows:

shall be plotted by its assigned order in the random sample, not by the order of testing). If (a) for each DTPG at any time the point plotted falls in the "Accept" region, testing of snubbers of that N > 36.49 + 18.18C type may be terminated. When the point plotted lies in the "Continue Testing" region, (b) for each FMG additional snubbers of that type shall be tested until the point falls in the "Accept" region or the NF > 18.18CF "Reject" region, or all the snubbers of that type have been tested; or

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 7 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Cu rrent,TS Surveillance Revised Snubber Progra m14siict. orCag Re~quirement,ý Requirement 4.7.10e. (continued) ISTD does not contain a 55 sample plan as an The revised snubber program for MPS3 does option. not contain the 55 sample plan shown in the

3) An initial representative sample of 55 SR 4.7.1Oe.3.

snubbers shall be functionally tested. For each snubber type which does not meet the functional test acceptance criteria, another sample of at least one-half the size of the initial sample shall be tested until the total number tested is equal to the initial sample size multiplied by the.factor, 1 + C/2, where "C" is the number of snubbers found which do not meet the functional test acceptance criteria.

The results from this sample plan shall be plotted using an "Accept" line which follows the equation N = 55(1 + C/2). Each snubber point should be plotted as soon as the snubber is tested. If the point plotted falls on or below the "Accept" line, testing o.f that type of snubber may be terminated. If the point plotted falls above the "Accept" line, testing must continue until the point falls in the "Accept" region or all' the snubbers of that type have been tested.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 8 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Curren't TS'Surveillance6'; Revised Snubber Program Justification for Change Requirement" Requirement 4.7.10e. (continued) ISTD has no similar provision. Snubber test equipment is calibrated daily when in use. If test equipment fails, Testing equipment failure during functional Measuring and Test Equipment (M&TE) testing may invalidate that day's testing and procedures require that items tested since the allow that day's testing to resume anew at a last calibration, be retested.

later time provided all snubbers tested with the failed equipment during the day of equipment failure are retested.

4.7.10e. (continued)

The representative sample selected for the ISTD-531 1(a) requires the initial sample to The revised snubber program requirements for functional test sample plans shall be randomly include as practicable representation from the sample selection are equivalent to SR 4.7.1Oe.

selected from the snubbers of each type and DTPG based on the significant features (i.e., requirements for representative random reviewed before beginning the testing. The the various designs, configurations, operating samples.

review shall ensure, as far as practicable, that environments, sizes, and capacities) and they are representative of the various based on the ratio of the number of snubbers configurations, operating environments, range of each significant feature, to the total number of size, and capacity of snubbers of each type. of snubbers in the DTPG. Initial sample Snubbers placed in the same location as selection shall be random.

snubbers which failed the previous functional test shall be retested at the time of the next ISTD-5500 requires that snubbers placed in The revised snubber program requirement is functional test but shall not be included in the the same location as snubbers that failed the equivalent to the current SR 4.7.10e.

sample plan. Ifduring the functional testing, previous inservice operational readiness test requirement to retest a replacement snubber additional sampling is required due to failure of shall be retested at the time of next operational installed in place of a failed snubber. Retesting only one type of snubber, the functional test readiness testing unless the cause of the is required, unless the cause of the original results shall be reviewed at that time to failure is clearly established and corrected. failure was clearly established and corrected.

determine ifadditional samples should be Any retest in accordance with this paragraph limited to the type of snubber which has failed shall not be considered a part of inservice the functional testing. operational readiness testing sample selection.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page"9 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Current TSSurveillance.

'Reqjuirementj 4 Revised Snubber Program TJustification for Cha Requirement .. ag 4.7.10f. Functional Test Acceptance Criteria ISTD-5210(a), (b) and (c) require the same The revised snubber program requirements for verification for operational readiness testing mechanical and hydraulic snubber acceptance The snubber functional test shall verify that: criteria are equivalent to those of current SR 4.7.1 Of.

1) Activation (restraining action) is achieved within the specified range in both tension and compression;

2) Snubber bleed, or release rate where required, is present in both tension and compression, within the specified range;

3) For mechanical snubbers, the force required to initiate or maintain motion of the snubber is within the specified range in both directions of travel; and

4) For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand load without displacement.

Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 10 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

CurrentTS Surveillance Revised Snubber Program Justification forChange-Requirement Requirement.

4.7.10g. Functional Test Failure Analysis ISTD-5271 states that snubbers that do not The revised snubber program requirements for meet test requirements shall be evaluated to determining the cause of each failure for testing An engineering evaluation shall be made of determine the root cause of the failure. snubbers with the potential for similar failures each failure to meet the functional test are similar to.those of current SR 4.7.10g.

acceptance criteria to determine the cause of ISTD-5272 states that snubbers found the failure. The results of this evaluation shall unacceptable according to operational readiness be used, if applicable, in selecting snubbers to test requirements should be assigned to FMGs be tested in an effort to determine the unless the failure is isolated or unexplained.

OPERABILITY of other snubbers irrespective of FMGs shall include all unacceptable snubbers type which may be subject to the same failure with the same failure mode and all other mode. snubbers with similar potential for similar failure.

For the snubbers found inoperable, an ISTD-1800 requires that an evaluation shall be The revised snubber program requirements to engineering evaluation shall be performed on performed of the system(s) or components of evaluate the system(s) or components of an the components to which the inoperable which an unacceptable snubber is a part, for unacceptable snubber are equivalent to those of snubbers are attached. The purpose of this possible damage to the supported system or current SR 4.7.10g.

engineering evaluation shall be to determine if component.

the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to The revised program requirements for ensure that the component remains capable of manufacturer or design deficiencies require meeting the designed service. replacement or modification of all snubbers in the FMG or additional testing until the If any snubber selected for functional testing As an alternative to additional testing for Design mathematical expression of ISTD-5331(b) is either fails to lock up or fails to move, i.e., or Manufacturing FMGs, ISTD-5323 requires no satisfied or all snubbers in the FMG have been frozen-in-place, the cause will be evaluated additional testing when all snubbers in the tested. This may result in fewer snubbers being and, if caused by manufacturer or design FMGs are replaced or modified in accordance tested after a test failure. However, the revised deficiency, all snubbers of the same type with ISTD-1 600. If replacement or modification is program requirements provide adequate subject to the same defect shall be functionally not performed in accordance with ISTD-5323, assurance of snubber OPERABILITY because tested. This testing requirement shall be additional testing is required in accordance with all potentially affected snubbers will be replaced independent of the requirements stated in ISTD 5324. Testing is required to continue until or modified; or the acceptance limit for Specification 4.7.10e. for snubbers not meeting the acceptance limit is satisfied or all snubbers additional testing will be met, demonstrating an the functional test acceptance criteria. in the FMG have been tested. acceptable level of reliability.

.j. ________________________________

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 11 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Current TS Surveillance Revised Snubber Programni J fi on f C

.Requirement' Requirement The revised snubber program requirement is 4.7.10h. Functional Testing of Repaired and ISTD-5280, Corrective Action, states that equivalent to the current TS SR 4.7.10h.

Replaced Snubbers unacceptable snubbers shall be adjusted requirement to retest modified or replacement repaired, modified, or replaced. The snubbers.

Snubbers which fail the visual inspection or the provisions of ISTD-1620 also apply.

functional test acceptance criteria shall be repaired or replaced. Replacement snubbers ISTD-1620 requires that replacement or and snubbers which have repairs which might modified snubbers are examined and tested.

affect the functional test results shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and the freedom-of-motion test must have been performed within 12 months before being installed in the unit.

Serial No.12-036 Docket No. 50-423 Attachment 4, Page 12 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

Current!TS Surveillance Requirement',

Revised SnubberlProgram Requirement I T tification fo Chang .

4.7.1Oi. Snubber Service Life Program ISTD-6100 requires initial snubber service life The service life evaluation requirements in to be predicted based on manufacturer's ISTD-6100 and ISTD-6200 are equivalent to The service life of hydraulic and mechanical recommendation or design review. the requirements in current TS SR 4.7.1Oi.

snubbers shall be monitored to ensure that the service life is not exceeded between ISTD-6200 requires service life to be evaluated surveillance inspections. The maximum at least once each fuel cycle. If the evaluation expected service life for various seals, springs, indicates that service life will be exceeded and other critical parts shall be determined and before the next scheduled system or plant established based on engineering information outage, one of the following actions shall be and shall be extended or shortened based on taken:

monitored test results and failure history.

Critical parts shall be replaced so that the (a) the snubber shall be replaced with a maximum service life will not be exceeded snubber for which the service life will during a period when the snubber is required not be exceeded before the next to be OPERABLE. The parts replacements scheduled system or plant outage shall be documented and the documentation shall be retained in accordance with Quality (b) technical justification shall be Assurance Program Topical Report. documented for extending the service life to or beyond the next scheduled system or plant outage (c) the snubber shall be reconditioned such that its service life will be extended to or beyond the next scheduled system or plant outage

Serial No.12-036 Docket No. 50-423 ATTACHMENT 5 U3-24-IST-SNUB-BAP01 SNUBBER EXAMINATION, TESTING. AND SERVICE LIFE MONITORING PROGRAM PLAN DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 Millstone Power Station Unit 3 U3-24-SNUB-BAPO1 Snubber Examination, Testing, and Service Life Monitoring Program Plan Revision 0 Commercial Service Date April 23, 1986 Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 Rope Ferry Road Waterford, CT 06385 APPROVALS:

See ER-MP-IST-106 Attachment 1 for approval signatures RevO0 Page / of 28 Date 02/1 Revision Date 4/1 2 02114112 Rev Page I of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 Revision Log Effective Revision Description Prepared: Date Approved: Date Date IST Snubber Engineering Coordinator Manager Original Eric Bookiniller 2/14/12 Doug Tilton for 2/22/12 Scott Smith

____ I ___________ I ______ I ___ _______ I RevO0 Page 2 of 28 Revision Date 02/I 4/1 2 02114112 Rev Page 2 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 TABLE OF CONTENTS SECTION

1.0 INTRODUCTION

1.1 Purpose 1.2 Scope 1.3 Discussion 2.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING REQUIREMENTS:

2.1 Snubber Inservice Testing Plan Description 2.2 DTPG Description 2.3 Service Life Monitoring 3.0 EXAMINATION and TESTING METHODS:

4.0 EXAMINATION and TESTING FREQUENCY:

5.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING EVAUATION:

6.0 REPAIR, REPLACEMENT, AND MODIFICATION REQUIREMENTS:

7.0 SCHEDULING

8.0 REPORTS AND RECORDS:

9.0 ATTACHMENTS

Rev 00 Page 3 of 28 Date 02/1 Revision Date 4/12 02114112 Rev Page 3 of 28

U3C-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 INTRODUCTION:

1.1 Purpose

To provide requirements for the performance and administration of assessing the operational readiness of those dynamic restraints (Snubbers) whose specific functions are required to perform one of the following three functions or, to ensure the integrity of the reactor coolant pressure boundary.

" Shutdown the reactor to the safe shutdown condition'

• Maintain the reactor in the safe shutdown condition

• Mitigate the consequences of an accident

1.2 Scope

The program plan was prepared to meet the requirements of the following subsections of the American Society of Mechanical Engineers (ASME) Code Section XI 2004 Edition and (ASME)

OM Code 2004 Edition.

• Subsection ISTA, "GeneralRequirements" ISTA contains the requirements directly applicable to inservice examination and testing including the Owner's Responsibility and Records Requirements.

• Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor NuclearPower Plants" ISTD establishes preservice and inservice examination and testing, and the service life of Dynamic Restraints (Snubbers) in light-water reactor nuclear power plants. The snubbers covered are required to support the systems and components that are required in shutting down a reactor to the safe shutdown condition, in maintaining the safe shutdown condition, or in mitigating the consequences of an accident.

• Section XI Article IWA-2213, "VT3 Examination" IWA-2213 establishes method for examination of snubbers in accordance with ISTD.

1.3 Discussion

In order to ensure the required operability of all safety related snubbers for Unit 3 during a seismic or other events, initiating dynamic loads, the inspection, testing, and the service life monitoring of these snubbers shall be implemented and performed in accordance with the requirements of SP 31138, Snubber Visual Inspection Surveillance and SP 31140 Snubber Functional Testing Surveillance.

The examination boundaries shall include the snubber assembly from pin to pin inclusive.

Coordination with the ISI program owner will be required to complete the surveillance requirements for piping and structural attachments. (Integral and nonintegral attachments for snubbers shall be examined in accordance with the requirements of the ASME Code Section XI, Article IWF-5200(c) and IWF-5300(c) within the ISI program.)

Revision Date 02114112 Rev 0 Page 4 o 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 The Snubber Program described in SP 31138 and SP 31140 adhere to the requirements of the ASME OM Code, Subsection ISTD, 2004 Edition, as allowed by I OCFR50.55a(b)(3)(v) in lieu of ASME Section XI, IWF-5200(a) and (b) and 1WF-5300(a) and (b).

2.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING REQUIREMENTS:

2.1 Visual Examinations, Functional Testing, and Service Life requirements shall be performed to the extent specified within SP 31138 and SP 31140.

2.2 Snubbers are grouped into Defined Test Plan Groups (DTPGs) by design type, in accordance with ISTD-5252. Each DTPG will be tested using the 10% sample plan or the 37 sample plan per ISTD-5300. The snubbers attached to the Steam Generators and Reactor coolant pumps are listed as a separate DTPG as required by ISTD-5253.

DTPGs at Millstone Station Unit 3 include all mechanical PSA snubbers size 1/4/4 and 1/2/2 as DTPG "A", all mechanical PSA snubbers size 1, 3, and 10 as DTPG "B", all mechanical PSA snubbers size 35 and 100 as DTPG "C", and all Steam Generator/Reactor Coolant Pump snubbers as DTPG "D".

The individual snubbers included in the each specific DTPG are listed in Attachments 9.1, 9.2, 9.3, and 9.4 of this plan.

2.4 The service life of all snubbers shall be monitored and snubbers replaced, reconditioned or evaluated in accordance with SP 31140 and ISTD-6200 to ensure that the service life is not exceeded between surveillance inspections. The replacement or reconditioning shall be documented and records retained in accordance with Millstone procedures.

3.0 EXAMINATION and TESTING METHODS:

3.1 Visual Examinations shall be performed by qualified individuals using the VT-3 method as described in ASME Section XI, IWA-2213. Visual Examinations and Functional Testing shall be performed to verify the requirements specified within SP 31138, SP 31140 and ER-AA-NDT-VT-603 are met in accordance with ISTD.

4.0 EXAMINATION and TESTING FREQUENCY:

4.1 Visual Examinations and Functional Testing shall be performed at the frequency specified within SP 31138 and SP 31140. Accessible and inaccessible snubber visual examinations are performed as one group with the frequency shown in Table ISTD 4252-1.

4.2 The Visual Examinations of Table ISTD 4252-1 may be extended in accordance with Code Case OMN13 once the prerequisites of the code case have been met.

4.3 Visual Examinations shall be performed whenever new snubbers are installed, reinstallation of existing or swapped snubbers that were functionally tested, or after repairs, replacements or modifications.

4.4 Functional testing requirements for new installations or spares shall be equal to or more stringent than that specified within SP 31140.

Page 5 of 28 Revision Revision Date 02/I 4/1 2 Date 02114112 Rev 0 Rev' 0 Page 5 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 5.0 EXAMINATION, TESTING AND SERVICE LIFE MONITORING EVAUATION:

5.1 Snubbers that do not appear to conform to the Visual Examination requirements of SP 31138, shall be reported for evaluation and appropriate corrective action.

5.2 Snubbers that do not appear to conform to the visual examination acceptance requirements and are later confirmed as operable as a result of functional testing may be declared operable for the purpose of establishing the next visual inspection interval, providing that the unacceptable condition did not affect operational readiness.

5.3 Snubbers that do not meet the operability testing acceptance criteria in SP 31140 shall be evaluated to determine the cause of the failure and appropriate corrective action taken.

5.4 The service life of a snubber is evaluated using manufacturing input and engineering information gained through consideration of the snubber service conditions and inservice functional test results.

A service life monitoring program is included in SP 31140.

6.0 REPAIR, REPLACEMENT, AND MODIFICATION REQUIREMENTS:

6.1 Repairs, Replacements and Modifications performed on snubbers under this program shall conform, as applicable, to the requirements specified within the ASME Code,Section XI, TWA 4000.

7.0 SCHEDULING

7.1 The Visual Examinations, Functional Testing schedules, and Service Life Replacements shall be established, tracked and maintained in accordance with SP 31138, SP 31140, and ISTD by the IST Snubber Coordinator.

7.2 The IST Snubber Coordinator shall identify and track expanded or additional testing and/or examinations as required by SP 31138, SP 31140 and ISTD.

8.0 REPORTS and RECORDS:

8.1 Reports and records for the Visual Examinations and Functional Testing shall be maintained for all snubbers included within the Snubber Program.

8.2 Applicable records and reports, as required for Repair and Replacements, shall be maintained for snubbers.

8.3 Records of the service life of all hydraulic and mechanical snubbers listed in this program, including the date at which the service life commences or expires, and associated installation and maintenance records will be maintained.

9.0 ATTACHMENTS

9.1 DPTG A (Mechanical Snubber PSA size 11/4 and 1/22 Test Group) 9.2 DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) 9.3 DPTG C (Mechanical Snubber PSA size 35 and 100 Test Group) 9.4 DPTG D (Steam Generator and Reactor Coolant Pump Snubber Test Group)

Revision Date 02114112 Rev 0 Page 6 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.1 DPTG A (Mechanical Snubber PSA size 14 and 1/2 Test Group) Pg 1 of 5 Hanger ID Number System Manufacturer Size Class Note 3BDG1 PSSP0406 BDG Basic PSA PSA-1/2 CL-2 3BDG1 PSSP0407 BDG Basic PSA PSA-1/2 CL-2 3BDG 1PSSP0414 BDG Basic PSA PSA-1/2 CL-2 3BDG1 PSSP0417 BDG Basic PSA PSA-1/2 CL-2 3BDG1 PSSP0429 BDG Basic PSA PSA-1/2 CL-2 3BDG1 PSSP0430 BDG Basic PSA PSA-1/2 CL-2 3BDG1 PSSP0433 BDG Basic PSA PSA-1/2 CL-2 3BDG1 PSSP0487 BDG Basic PSA PSA-1/4 CL-4 SIB 3BDG1 PSSP0489 BDG Basic PSA PSA-1/4 CL-4 SIB 3BDG1 PSSP0491 BDG Basic PSA PSA-1/4 CL-4 SIB 3BDG1 PSSP0492 BDG Basic PSA PSA-1/4 CL-4 SIB 3BDGl PSSP0495 BDG Basic PSA PSA-1/4 CL-4 SIB 3BDG1 PSSP0496 BDG Basic PSA PSA-1/4 CL-4 SIB 3CHS1 PSSP0605 CHG Basic PSA PSA-1/4 CL-2.

3CHS1PSSP0608 CHG Basic PSA PSA-1/2 CL-2 3CHS1PSSP0707 CHG Basic PSA PSA-1/4 CL-2 3CHS1 PSSP0718 CHG Basic PSA PSA-1/4 CL-2 3CHS1 PSSP0721 CHG Basic PSA PSA-1/4 CL-2 3CHS1 PSSP0726 CHG Basic PSA PSA-1/4 CL-2 3CHS1PSSP0727 CHG Basic PSA PSA-1/4 CL-2 3CHS1PSSP0728 CHG Basic PSA PSA-1/4 CL-2 3CHS1PSSP0740 CHG Basic PSA PSA-1/4 CL-1 3CHS1 PSSP0744 CHG Basic PSA PSA-1/4 CL-2 3CHS1 PSSP0992 CHG Basic PSA PSA-1/2 CL-2 3CHS1PSSP0993 CHG Basic PSA PSA-1/4 CL-2 3CHS1 PSSP1033 CHG Basic PSA PSA-1/4 CL-2 3CHS1PSSP1034 CHG Basic PSA PSA-1/2 CL-2 3CHS1PSSP1036 CHG Basic PSA PSA-1/2 CL-2 3CHS2PSSPO410 CHG Basic PSA PSA-1/2 CL-2 3CHS2PSSP0411 CHG Basic PSA PSA-1/4 CL-2 3CHS2PSSP0412 CHG Basic PSA PSA-1/4 CL-2 3CHS2PSSP0441 CHG Basic PSA PSA-1/4 CL-2 3CHS2PSSP0441 CHG Basic PSA PSA-1/4 CL-2 3CHS2PSSP0455 CHG Basic PSA PSA-1/4 CL-2 3CHS2PSSP0456 CHG Basic PSA PSA-1/2 CL-2 3CHS2PSSP0467 CHG Basic PSA PSA-1/2 CL-2 3CHS2PSSP0468 CHG Basic PSA PSA-1/2 CL-2 3CSS2 PSSP0456 STG Basic PSA PSA-1/2 CL-2 3MSS1 PSSP0459 STG Basic PSA PSA-1/2 CL-2 3MSS1 PSSP0460 STG Basic PSA PSA-1/2 CL-2 3MSS1 PSSP0465 STG Basic PSA PSA-1/2 CL-2 3MSS1 PSSP0466 STG Basic PSA PSA-1/2 CL-2 3MSS1 PSSP0467 STG Basic PSA PSA-1/2 CL-2 3MSS1 PSSP0471 STG Basic PSA PSA-1/2 CL-2 3MSS1PSSP0472 STG Basic PSA PSA-1/4 CL-2 Page 7 of 28 02/I 4/1 2 Revision Date 02114112 Revision Rev 00 Rev Page 7 qf '28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.1 (cont)

DPTG A (Mechanical Snubber PSA size 1/4 and 1/2/Test Group) Pg 2 of 5 Hanger ID Number System Manufacturer Size Class Note 3MSS4PSSPOO02 STG Basic PSA PSA-1/4 CL-3 3MSS4PSSPO0O07 STG Basic PSA PSA-1/4 CL-3 3MSS4PSSPOO1 1 STG Basic PSA PSA-1/4 CL-3 3MSS4PSSP0O35 STG Basic PSA PSA-1/4 CL-3 3MSS4PSSP0040 STG Basic PSA PSA-1/4 CL-3 3MSS4PSSP0O42 STG Basic PSA PSA-1/4 CL-3 3RCS11PSSP1520 RCS Basic PSA PSA-1/2 CL-2 3RCSl PSSP0027 RCS Basic PSA PSA-1/4 CL-2 3RCS1 PSSP0039 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSPOO44 RCS Basic PSA PSA-1/2 CL-1 3RCSl PSSP0046 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSP0106 RCS Basic PSA PSA-1/2 CL-1 3RCS1PSSP01 10 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP01 11 RCS Basic PSA PSA-1/2 CL-1 3RCS1 PSSPO113 RCS Basic PSA PSA-1/2 CL-1 3RCS1PSSPO0114 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0118 RCS Basic PSA PSA-1/4 CL-1 3RCStPSSP01 19 RCS Basic PSA PSA- 1/4 CL-1 3RCSlPSSP0120 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSP0121 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0122 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0126 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0128 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0129 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0130 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0132 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0133 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0137 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSP0138 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSPO144 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSP0145 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSP0149 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSP0152 RCS Basic PSA PSA-1/2 CL-1 3RCSlPSSP0153 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0156 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0162 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0163 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0164 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP0167 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0168 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0639 RCS Basic PSA PSA-1/2 CL-1 3RCS1 PSSP0729 RCS Basic PSA PSA-1/2 CL-1 3RCS1 PSSP0807 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0913 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0915 RCS Basic PSA PSA-1/4 CL-1 Page 8 of 28 02/14/12 Revision Date 02114112 Rev 00 Rev Page 8 oj' 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.1 (cont)

DPTG A (Mechanical Snubber PSA size 1/4/and 1/2 Test Group) Pg 3 of 5 Hanger ID Number System Manufacturer Size Class Note 3RCS1 PSSP0916 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0917 RCS Basic PSA PSA-1/2 CL-1 3RCS1 PSSP0918 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0920 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0921 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0922 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0924 RCS Basic PSA PSA-1 /2 CL-1 3RCS1PSSP0925 RCS Basic PSA PSA-1 /4 CL-1 3RCS1 PSSP0926 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0928 RCS Basic PSA PSA-1/2 CL-1 3RCS1 PSSP0929 RCS Basic PSA PSA-1/2 CL-1 3RCS1PSSP0930 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0931 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0932 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0937 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0938 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0939 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0941 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0943 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0945 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0946 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0959 RCS Basic PSA PSA-1/2 CL-1 3RCS1PSSP0962 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0963 RCS Basic PSA PSA-1/4 CL-i 3RCS1 PSSP0965 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0966 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0967 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0968 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0969 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0970 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0971 RCS Basic PSA PSA-1/2 CL-i 3RCS1 PSSP0972 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP0973 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0975 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0976 RCS Basic PSA PSA-1/4 CL-1 3RCSl PSSP0977 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0978 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0979 RCS Basic PSA PSA-1/2 CL-1 3RCS1 PSSP0980 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP0981 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP1018 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP1019 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP1021 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP1022 RCS Basic PSA PSA- 1/4 CL-i 3RCSlPSSP1023 RCS Basic PSA PSA-1/4 CL-i Page 9 of 28 Revision Date Revision 02/1 4/12 Date 02114112 Rev 0 Rev 0 Page 9 of 28

, U3-24-SNUB-BAPOI Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.1 (cont)

DPTG A (Mechanical Snubber PSA size 1/4/and 1/1/2 Test Group) Pg 4 of 5 Hanger ID Number System Manufacturer Size Class Note 3RCS1PSSP1037 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP1038 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP1039 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP1040 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP1041 RCS Basic PSA PSA-1/4 CL-1 3RCSiPSSP1045 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP1063 RCS Basic PSA PSA-1/4 CL-1 3RCS1PSSP1 113 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP1 114 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP1116 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP1 119 RCS Basic PSA PSA-1/4 CL-1 3RCS1 PSSP1 231 RCS Basic PSA PSA-1/4 CL:I 3RCSlPSSP1233 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP1235 RCS Basic PSA PSA-1/4 CL-1 3RCSlPSSP1237 RCS Basic PSA PSA-1/4 CL-1 3RCSlVPSSP1517 RCS Basic PSA PSA-1 /2 CL-1 3RCS1VPSSP1518 RCS Basic PSA PSA-1/2 CL-1 3RCS1VPSSP1522 RCS Basic PSA PSA-1/2 CL-1 3RCSlVPSSP1523 RCS Basic PSA PSA-1/2 CL-1 3RCSlVPSSP1524 RCS Basic PSA PSA-1/2 CL-1 3RCSlVPSSP1525 RCS Basic PSA PSA-1/2 CL-1 3RCSlVPSSP1526 RCS Basic PSA PSA-1/2 CL-1 3RCS1VPSSP1527 RCS Basic PSA PSA-1 /2 CL-1 3RHS4PSSP0402 RHR Basic PSA PSA-1/2 CL-2 3RHS4PSSP0444 RHR Basic PSA PSA-1/4 CL-2 3SIHlPSSP0142 HPI Basic PSA PSA-1/4 CL-1 3SIH1PSSP0143 HPI Basic PSA PSA-1/2 CL-1 3SIH1PSSP0157 HPI Basic PSA PSA-1/4 CL-1 3SIHlPSSP0158 HPI Basic PSA PSA-1/2 CL-1 3SIHlPSSP0159 HPI Basic PSA PSA-1/2 CL-1 3SIHl PSSP0450 HPI Basic PSA PSA-1/2 CL-1 3SIHlPSSP1029 HPI Basic PSA PSA-1/2 CL-1 3SIH1PSSP1030 HPI Basic PSA PSA-1/2 CL-1 3SIHl PSSP1044 HPI Basic PSA PSA-1/2 CL-1 3SIH1PSSP1 102 HPI Basic PSA PSA-1/4 CL-1 3SIHi PSSP1 110 HPI Basic PSA PSA-1/4 CL-1 3SILlPSSP0450 LPI Basic PSA PSA-1/2 CL-2 3SILlPSSP1028 LPI Basic PSA PSA-1/4 CL-2 CP302760H004 STG Basic PSA PSA-1/4 CL-4 SIB CP302760H006 STG Basic PSA PSA-1/4 CL-4 SIB CP302760H010 STG Basic PSA PSA-1/4 CL-4 SIB CP302761 H004 STG Basic PSA PSA-1/4 CL-4 SIB CP302761HOO5 STG Basic PSA PSA-1/4 CL-4 SIB CP302761 H009 STG Basic PSA PSA-1/4 CL-4 SIB Rev 00 Page 10of28 Date 02/1 Revision Date 4/12 02114112 .Rev Page 10 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.1 (cont)

DPTG A (Mechanical Snubber PSA size 1/4 and 1/22Test Group) Pg 5of 5 Hanger ID Number System Manufacturer Size Class Note CP302762H001 STG Basic PSA PSA-1/4 CL-3 CP302762H012 STG ,Basic PSA PSA-1/4 CL-3 CP302763H004 STG Basic PSA PSA-1/4 CL-4 SIB CP302763H008 STG Basic PSA PSA-1/4 CL-4 SIB CP302763H012 STG Basic PSA PSA-1/4 CL-4 SIB CP371500HOOl RHS Basic PSA PSA-1/4 CL-2 CP394044H005 DTM Basic PSA PSA-1/4 CL-2 CP394045H001 DTM Basic PSA PSA-1/4 CL-2 CP394045H004 DTM Basic PSA PSA-1/4 CL-2 CP394045H005 DTM Basic PSA PSA-1/2 CL-2 CP394045H010 DTM Basic PSA PSA-1/4 CL-2 CP394052H001 DTM Basic PSA PSA-1/4 CL-2 CP394052H005 DTM Basic PSA PSA-1/4 CL-2 CP394052H006 DTM Basic PSA PSA-1/4 CL-2 CP394052H008 DTM Basic PSA PSA-1/4 CL-2 CP408051 H003 BDG Basic PSA PSA-1/4 CL-4 SIB CP408051 H006 BDG Basic PSA PSA-1/4 CL-4 SIB CP408052H003 BDG Basic PSA PSA- 1/4 CL-4 SIB CP408052H006 BDG Basic PSA PSA-1/4 CL-4 SIB CP408053H003 BDG Basic PSA PSA-1/4 CL-4 SIB CP408054H001 BDG Basic PSA PSA-1/4 CL-4 SIB CP408054H003 BDG Basic PSA PSA-1/4 CL-4 SIB CP408055H002 BDG Basic PSA PSA-1/4 CL-2 CP408056H001 BDG BasicýPSA PSA-1/4 CL-2 CP408057H001 BDG Basic PSA PSA-1/4 CL-2 CP408057H002 BDG Basic PSA PSA-1/4 CL-2 CP408058H004 BDG Basic PSA PSA-1/4 CL-2 CP409004H006 RCS Basic PSA PSA-1/4 CL-2 CP409004H010 RCS Basic PSA PSA-1/4 CL-2 CP409005H010 RCS Basic PSA PSA-1/4 CL-4 SIB CP409005H012 RCS Basic PSA PSA-1/4 CL-4 SIB CP409005H013 RCS Basic PSA PSA-1/2 CL-2 CP409005H015 RCS Basic PSA PSA-1/4 CL-2 CP409701H009 RCS Basic PSA PSA-1/4 CL-2 CP409701 H01 6 RCS Basic PSA PSA-1/4 CL-2 Notes SIB Non-QA Snubbers which constitute the Seismic Interface Boundary are labeled as "SIB" and are required to be included in the Surveillance Program as required by Specification SP-ME-570.

QA-DF and SIB-DF Dual Function snubbers which are Pipe Supports/Rupture Restraints are labeled as QA-DF or SIB-DF and are required to be included in the Surveillance Program as required by Specification SP-ME-570.

Rev 00 Page 11 of 28 Revision Date 02/14/12 Revision 02114172 Rev Page I11 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 1 of 13 Hanger ID Numbei System Manufacturer Size Class Note 3BDG1 PSSP0400 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP040i BDG Basic PSA PSA-1 CL-2 3BDG 1PSSP0402 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0403 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0404 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0408 BDG Basic PSA PSA-1L CL-2 3BDG1 PSSP0409 BDG Basic PSA PSA-1L CL-2 3BDG1 PSSP0411 BDG Basic PSA PSA-1L CL-2 3BDG 1PSSP0412 BDG Basic PSA PSA-1 CL-2 3BDG 1PSSP0413 BDG Basic PSA PSA-1 CL-2 3BDG 1PSSP0416 BDG Basic PSA PSA-1 L CL-2 3BDG 1PSSP0418 BDG Basic PSA PSA-1 L CL-2 3BDG 1PSSP0419 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0420 BDG Basic PSA PSA-1 L CL-2 3BDG1 PSSP0421 BDG Basic PSA PSA-1 L CL-2 3BDG1 PSSP0422 BDG Basic PSA PSA-1L CL-2 3BDG1 PSSP0423 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0424 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0426 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0427 BDG Basic PSA PSA-1 CL-2 3BDG1PSSP0428 BDG Basic PSA PSA-1 CL-2 3BDG 1PSSP0431 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0432 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0461 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0462 BDG Basic PSA PSA-1 L CL-2 3BDG1 PSSP0463 BDG Basic PSA PSA-1 L CL-2 3BDG1 PSSP0479 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0480 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0481 BDG Basic PSA PsA-1 CL-4 SIB 3BDG1 PSSP0483 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0484 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0485 BDG Basic PSA PSA-1 CL-2 3BDG1 PSSP0488 BDG Basic PSA PSA-1 CL-4 SIB 3BDG1 PSSP0493 BDG Basic PSA PSA-1 CL-4 SIB 3BDG1 PSSP0508 BDG Basic PSA PSA-1 CL-2 3BDG4PSSPOO47 BDG Basic PSA PSA-10 CL-4 SIB-DF 3BDG4PSSPOO50 BDG Basic PSA PSA-10 CL-4 SIB-DF 3BDG4PSSPOO53 BDG Basic PSA PSA-10 CL-4 SIB-DF 3BDG4PSSPOO56 BDG Basic PSA PSA-10 CL-4 SIB-DF 3BDG4PSSP0200 BDG Basic PSA PSA-10 CL-4 SIB-DF 3BDG4PSSP0201 BDG Basic PSA PSA-10 CL-4 SIB-DF 3BDG4PSSP0202 BDG Basic PSA PSA-10 CL-4 SIB-DF 3BDG4PSSP0203 BDG Basic PSA PSA-10 CL-4 SIB-DF 3CCP2PSSP0400 CCP Basic PSA PSA-3 CL-3 3CCP2PSSP0401 CCP Basic PSA PSA-3 CL-3 Rev 00 Page 12 of 28 Revision Date 02/14/12 02114172 Rev Page 12 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 2 of 13.

Hanger ID Number System Manufacturer Size Class Note 3CCP2PSSP0405 CCP Basic PSA PSA-3 CL-3 3CCP2PSSP0406 CCP Basic PSA PSA-3 CL-3 3CCP2PSSP0414 CCP Basic PSA PSA-10 CL-3 3CCP2PSSP0415 CCP Basic PSA PSA-10 CL-3 3CCP4PSSP0400 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0401 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0403 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0404 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0407 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0411 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0412 CCP Basic PSA PSA-10 CL-3 3CCP4PSSP0413 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0414 CCP Basic PSA PSA-3 CL-3 3CCP4PSSP0415 CCP Basic PSA PSA-3 CL-3 3CHS1PSSP0551 CHG Basic PSA PSA-10 CL-2 QA-DF 3CHS1PSSP0552 CHG Basic PSA PSA-10 CL-2 QA-DF 3CHS1 PSSP0610 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0611 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0613 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0626 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0635 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0644 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0645 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0649 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0650 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0653 CHG Basic PSA PSA-i CL-2 3CHS1 PSSP0704 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0705 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0706 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0711 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP0712 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0719 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0720 CHG Basic PSA PSA-1 CL-2 3CHS1 PSSP0742 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP1035 CHG Basic PSA PSA-1 CL-2 3CHS1PSSP1058 CHG Basic PSA PSA-1 CL-2 3CHS2PSSP0400 CHG Basic PSA PSA-1 CL-2 3CHS2PSSP0401 CHG Basic PSA PSA-1 CL-2 3CHS2PSSP0402 CHG Basic PSA PSA-1 CL-2 3CHS2PSSP0413 CHG Basic PSA PSA-1 CL-2 3CHS2PSSP0414 CHG Basic PSA PSA-1 CL-2 3CHS2PSSP0460 CHG Basic PSA PSA-3 CL-2 3CHS2PSSP0461 CHG Basic PSA PSA-3 CL-2 3CHS2PSSP0466 CHG Basic PSA PSA-3 CL-2 3DTM4PSSPOO27 DTM Basic PSA PSA-1 CL-2 Rev 00 Page 13 of 28 Revision Date 02/I 4/1 2 Date 02114112 Rev Page 13 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 3 of 13 Hanger ID Number System Manufacturer Size Class Note 3DTM4PSSPOO30 DTM Basic PSA PSA-1 CL-2 3DTM4PSSPOO39 DTM Basic PSA PSA-1 CL-2 3DTM4PSSPOO42 DTM Basic PSA PSA-1 CL-2 3DTM4PSSPOO51 DTM Basic PSA PSA-1 CL-2 3DTM4PSSPOO54 DTM Basic PSA PSA-1 CL-2 3DTM4PSSPOO63 DTM Basic PSA PSA-1 CL-2 3DTM4PSSPOO66 DTM Basic PSA PSA-1 CL-2 3EGD6PSSPOO01 DGN Basic PSA PSA-3 CL-3 3EGD6PSSPOO03 DGN Basic PSA PSA-3 CL-3 3EGD6PSSPOO10 DGN Basic PSA PSA-10 CL-4 SIB 3EGD6PSSPOO13 DGN Basic PSA PSA-3 CL-3 3EGD6PSSPOO15 DGN Basic PSA PSA-3 CL-3 3EGD6PSSPOO22 DGN Basic PSA PSA-10 CL-4 SIB 3EGD6PSSPOO25 DGN Basic PSA PSA-10 CL-4 SIB 3EGD6PSSPOO26 DGN Basic PSA PSA-10 CL-4 SIB 3FWA1 PSSP0400 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0401 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0402 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0403 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0404 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0405 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0406 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0407 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0408 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0409 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP041 0 AFW Basic PSA PSA-3 CL-2 3FWA1PSSP0411 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0412 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0413 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0414 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0415 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0416 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0417 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0418 AFW Basic PSA PSA-3 CL-2 3FWA1 PSSP0419 AFW Basic PSA PSA-1 CL-2 3FWA1 PSSP0420 AFW Basic PSA PSA-3 CL-2 3FWA4PSSP0936 AFW Basic PSA PSA-3 CL-2 QA-DF 3FWS1 PSSP0402 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0403 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0404 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0413 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0414 FWS Basic PSA PSA-10 CL-2 3FWS1PSSP0415 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0426 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0427 FWS Basic PSA PSA-10 CL-2 RevO Page 14 of 28 Revision Date 02/I 4/i 2 Date 02114112 Rev 0 Page 14 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 4 of 13 Hanger ID Number System Manufacturer Size Class Note 3FWS1 PSSP0429 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0430 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0431 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0432 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0437 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0438 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0440 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0441 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0442 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0443 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0444 FWS Basic PSA PSA-10 CL-2 3FWS1 PSSP0445 FWS Basic PSA PSA-10 CL-2 3FWS4PSSP0401 FWS Basic PSA PSA-3 CL-2 3FWS4PSSP0402 FWS Basic PSA PSA-3 CL-3 3FWS4PSSP0403 FWS Basic PSA PSA-3 CL-3 3FWS4PSSP0404 FWS Basic PSA PSA-3 CL-3 31C11PSSPOO05 IMS Basic PSA PSA-3 CL-1 31C11PSSPOO06 IMS Basic PSA PSA-3 CL-1 3MSS1 PSSP0438 STG Basic PSA PSA-10 CL-2 3MSS1 PSSP0442 STG Basic PSA PSA-10 CL-2 3MSS1 PSSP0457 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0458 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0461 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0462 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0463 STG Basic PSA PSA-1L CL-2 3MSS1 PSSP0464 STG Basic PSA PSA-1L CL-2 3MSS1 PSSP0468 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0469 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0470 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0473 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0474 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0555 STG Basic PSA PSA-3 CL-2 3MSS1 PSSP0558 STG Basic PSA PSA-1 CL-2 3MSS1 PSSP0559 STG Basic PSA PSA-1 CL-2 3MSS4PSSPOO03 STG Basic PSA PSA-3 CL-2 3MSS4PSSPOO06 STG Basic PSA PSA-3 CL-2 3MSS4PSSPOO09 STG Basic PSA PSA-I CL-3 3MSS4PSSPOO13 STG Basic PSA PSA-1 CL-2 3MSS4PSSPOO14 STG Basic PSA PSA-3 CL-2 3MSS4PSSPOO17 STG Basic PSA PSA-3 CL-2 3MSS4PSSPOO22 STG Basic PSA PSA-1 CL-2 3MSS4PSSPOO23 STG Basic PSA PSA-3 CL-2 3MSS4PSSPOO24 STG Basic PSA PSA_3' CL-2 3MSS4PSSPOO26 STG Basic PSA PSA-1 CL-2 3MSS4PSSPOO28 STG Basic PSA PSA-1 CL-3 Page 15 of 28 02/14/12 Revision Date 02114112 Rev 00 Rev Page 15 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 5 of 13 Hanger ID Number System Manufacturer Size Class Note 3MSS4PSSPOO37 STG Basic PSA PSA-3 CL-2 3MSS4PSSPOO60 STG Basic PSA PSA-1 CL-2 3MSS4PSSP0102 STG Basic PSA PSA-3 CL-2 3MSS4PSSPO1 11 STG Basic PSA PSA-3 CL-2 3MSS4PSSP01 13 STG Basic PSA PSA-3 CL-2 3MSS4PSSP0122 STG Basic PSA PSA-3 CL-2 3MSS4PSSP0482 STG Basic PSA PSA-3 CL-2 3MSS4PSSP0483 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0484 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0485 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0486 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0487 STG Basic PSA PSA-1 CL-2 3MSS4PSSP0488 STG Basic PSA PSA-1 CL-2 3MSS4PSSP0489 STG Basic PSA PSA-1 CL-2 3MSS4PSSP0490 STG Basic PSA PSA-1 CL-2 3MSS4PSSP0491 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0492 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0493 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0494 STG Basic PSA PSA-1 CL-3 3MSS4PSSP0495 STG Basic PSA PSA-3 CL-2 3MSS5PSSP0413 STG Basic PSA PSA-10 CL-4 SIB 3MSS5PSSP0414 STG Basic PSA PSA-10 CL-4 SIB 3MSS5PSSP0418 STG Basic PSA PSA-10 CL-4 SIB 3MSS5PSSP0497 STG Basic PSA PSA-10 CL-4 SIB 3QSS1PSSP0142 ass Basic PSA PSA-10 CL-2 3QSS1PSSP0400 ass Basic PSA PSA-10 CL-2 3QSS1 PSSP0401 ass Basic PSA PSA-10 CL-2 3QSSl PSSP0402 QSS Basic PSA PSA-3 CL-2 3QSS1 PSSP0403 ass Basic PSA PSA-3 CL-2 3QSS1PSSP0404 QSS Basic PSA PSA-3 CL-2 3QSS1PSSP0405 ass Basic PSA PSA-3 CL-2 30SS1PSSP0406 Qss Basic PSA PSA-3 CL-2 3Q.SS1PSSP0408 ass Basic PSA PSA-3 CL-2 3QSS1PSSP0409 ass Basic PSA PSA-3 CL-2 3QSS1 PSSP0410 ass Basic PSA PSA-3 CL-2 3QSS1 PSSP0411 ass Basic PSA PSA-3 CL-2 3QSS1PSSP0420 ass Basic PSA PSA-3 CL-2 3QSS 1PSSP0421 ass Basic PSA PSA-3 CL-2 3QSS1PSSP0448 ass Basic PSA PSA-10 CL-2 3QSS1 PSSP0449 ass Basic PSA PSA-3 CL-2 3QSS1 PSSP0450 ass Basic PSA PSA-3 CL-2 3QSS1PSSP0451 ass Basic PSA PSA-3 CL-2 3QSS1PSSP0453 ass Basic PSA PSA-10 CL-2 3QSS1PSSP0454 ass Basic PSA PSA-10 CL-2 3QSS1 PSSP0459 ass Basic PSA PSA-10 CL-2 Rev 00 Page 16 of 28 Date 02/1 Revision Date 4/12 02114112 Rev Page 16 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 6 of 13 Hanger ID Number System Manufacturer Size Class Note 3QSS1 PSSP0460 ass Basic PSA PSA-10 CL-2 3QSSl PSSP0469 ass Basic PSA PSA-3 CL-2 3QSS4PSSP0400 ass Basic PSA PSA-3 CL-2 3QSS4PSSP0401 ass Basic PSA PSA-3 CL-2 3RCS1 IPSSP1 519 RCS Basic PSA PSA-1 CL-2 3RCS1 PSSP0009 RCS Basic PSA PSA-1 CL-1 3RCSlPSS P0012 RCS Basic PSA PSA-1 CL-1 3RCSlPSSPOO14 RCS Basic PSA PSA-1 CL-1 3RCSlPSSPOO16 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0019 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0021 RCS Basic PSA PSA-3 CL-1 3RCSl PSSPO022 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0032 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0035 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP0055 RCS Basic PSA PSA-3 CL-1 3RCSlPSSPOO56 RCS Basic PSA PSA-1 CL-1 3RCSl PSSPOO58 RCS Basic PSA PSA-3 CL-1 3RCS1 PSSP0061 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0062 RCS Basic PSA PSA-1 CL-1 3RCSl PSSPOO64 RCS Basic PSA PSA-1 CL-1 3RCSl PSSPOO65 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSPOO80 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSPOO81 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSPOO82 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSP0083 RCS Basic PSA PSA-10 CL-4 SIB 3RCSl PSSPOO84 RCS Basic PSA PSA-10 CL-4 SIB 3RCSl PSSPOO86 RCS Basic PSA PSA-3 CL-4 SIB 3RCSl PSSPOO87 RCS Basic PSA PSA-3 CL-4 SIB 3RCSlPSSPOO88 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1PSSP0089 RCS Basic PSA PSA-10 CL-4 SIB 3RCS1 PSSP0090 RCS Basic PSA PSA-10 CL-4 SIB 3RCS1 PSSP0091 RCS Basic PSA PSA-3 CL-4 SIB 3RCSl PSSPOO92 RCS Basic PSA PSA-3 CL-4 SIB 3RCSl PSSPOO94 RCS Basic PSA PSA-10 CL-4 SIB 3RCSl PSSPOO95 RCS Basic PSA PSA-10 CL-4 SIB 3RCSl PSSPOO96 RCS Basic PSA PSA-10 CL-4 SIB 3RCSl PSSP0097 RCS Basic PSA PSA-10 CL-4 SIB 3RCSl PSSPOO98 RCS Basic PSA PSA-10 CL-4 SIB 3RCSl PSSPOO99 RCS Basic PSA PSA-3 CL-4 SIB 3RCSlPSSP0101 RCS Basic PSA PSA-1 CL-4 SIB 3RCSl PSSP0103 RCS Basic PSA PSA-1 CL-4 SIB 3RCSl PSSP0104 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0105 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0107 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0112 RCS Basic PSA PSA-1 CL-1 RevO Page 17of28 Rei'ision Date 02/1 Revision Date 4/12 02114112 Rev 0 Page 17 of 28

U3-24-SNUB-BAPOl Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 7 of 13 Hanger ID Number System Manufacturer Size Class Note 3RCS1PSSP0116 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP01 17 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0125 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0134 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0146 RCS Basic PSA PSA-3 CL-1 3RCS1PSSP0147 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP0150 RCS Basic PSA PSA-3 CL-1 3RCS1PSSP0155 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0165 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0166 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0445 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0446 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0447 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0460 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0461 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0521 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP0523 RCS Basic PSA PSA-10 CL-1 3RCS1PSSP0525 RCS Basic PSA PSA-10 CL-1 3RCSl PSSP0526 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP0527 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP0528 RCS Basic PSA PSA-10 CL-1 3RCSlPSSP0529 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP0530 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP0532 RCS Basic PSA PSA-3 CL-1 3RCSl PSSP0606 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0607 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0608 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0640 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0641 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0642 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0643 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0646 RCS Basic PSA PSA-1 CL-1 3RCS1PSSP0647 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0648 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0804 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0806 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0809 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSP0810 RCS Basic PSA PSA-1 CL-4 SIB 3RCS1 PSSP0811 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0812 RCS Basic PSA PSA-3 CL-4 SIB 3RCSlPSSP0813 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSP0815 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSP0816 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSP0819 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0820 RCS Basic PSA PSA-3 CL-4 SIB RevO0 Page 18of28 Date 02/1 Revision Date 4/12 02114112 Rev Page 18 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 8 of 13 Hanger ID Number System Manufacturer Size Class Note 3RCSlPSSP0821 RCS Basic PSA PSA-3 CL-4 SIB 3RCSlPSSPO822 RCS Basic PSA PSA-3 CL-4 SIB 3RCSl PSSP0824 RCS Basic PSA PSA-3 CL-4 SIB 3RCSlPSSP0825 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0827 RCS Basic PSA PSA-1 CL-4 SIB 3RCS1 PSSP0828 RCS Basic PSA PSA-1 CL-4 SIB 3RCS1PSSP0829 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0830 RCS Basic PSA PSA-3 CL-4 SIB 3RCS1 PSSP0831 RCS Basic PSA PSA-1 CL-4 SIB 3RCSl PSSP0832 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP0834 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0835 RCS Basic PSA PSA-1 CL-1 3RCS1PSSP0836 RCS Basic PSA PSA-3 CL-1 3RCS1PSSP0837 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0838 RCS Basic PSA PSA-1 CL-4 SIB 3RCSl PSSP0839 RCS Basic PSA PSA-3 CL-4 SIB 3RCSlPSSP0840 RCS Basic PSA PSA-3 CL-4 SIB 3RCSlPSSP0841 RCS Basic PSA PSA-3 CL-4 SIB 3RCSl PSSP0842 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0844 RCS Basic PSA PSAK-1 CL-1 3RCSl PSSP0845 RCS Basic PSA PSA-3 CL-1 3RCSl PSSP0849 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0851 RCS Basic PSA PSA-1 CL-1 3RCS1PSSP0855 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0859 RCS Basic PSA PSA-1 CL-4 SIB 3RCSlPSSP0914 RCS Basic PSA PSA-1 CL-1 3RCS1 PSSP0923 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0927 RCS Basic PSA PSA-1L CL-1 3RCSl PSSP0933 RCS Basic PSA PSA-1L CL-1 3RCSIPSSP0934 RCS Basic PSA PSA-1L CL-1 3RCS1 PSSP0935 RCS Basic PSA PSA-1L CL-1 3RCSlPSSP0936 RCS Basic PSA PSA-1L CL-1 3RCSl PSSP0947 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0948 RCS Basic PSA PSA-1 CL-1 3RCSl PSSP0992 RCS Basic PSA PSA-10 CL-1 QA-DF 3RCSl PSSP0993 RCS Basic PSA PSA-10 CL-1 QA-DF 3RCSl PSSP1009 RCS Basic PSA PSA-1L CL-1 3RCSlPSSP1010 RCS Basic PSA PSA-1L CL-1 3RCS1PSSPi1011 RCS Basic PSA PSA-1L CL-1 3RCS1PSSP1020 RCS Basic PSA PSA-i CL-1 3RCS1PSSP1024 RCS Basic PSA PSA-1 CL-1 3RCS1PSSP1025 RCS Basic PSA PSA-1L CL-1 3RCSlPSSP1026 RCS Basic PSA PSA-3 CL-1 3RCSlPSSP1068 RCS Basic PSA PSA-1 CL-1 3RCSlPSSP1092 RCS Basic PSA PSA-3 CL-4 SIB Rev 00 Page 19 of 28 Date 02/1 Revision Date 4/1 2 02114112 Rev Page 19 of 28

U3-24-SNUB-BAPO]

Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 9 of 13 Hanger ID Number System Manufacturer Size Class Note 3RCSlPSSP1093 RCS Basic PSA PsA-3 CL-4 SIB 3RCS1 PSSP1 117 RCS Basic PSA PSA-1L CL-1 3RHS1PSSP0402 RHR Basic PSA PSA-10 CL-1 3RHSlPSSP0408 RHR Basic PSA PSA-3 CL-1 3RHSlPSSP0409 RHR Basic PSA PSA-3 CL-1 3RHS1 PSSP041i0 RHR Basic PSA PSA-10 CL-1 3RHS1 PSSP0411 RHR Basic PSA PSA-10 CL-1 3RHS1 PSSP0414 RHR Basic PSA PSA-3 CL-1 3RHSl PSSP0420 RHR Basic PSA PSA-10 CL-1 3RHSlPSSP0421 RHR Basic PSA PSA-10 CL-1 3RHSiPSSP0423 RHR Basic PSA PSA-3 CL-1 3RHS1PSSP0424 RHR Basic PSA PSA-10 CL-1 3RHS4PSSPOO06 RHR Basic PSA PSA-10 CL-2 3RHS4PSSP0400 RH R Basic PSA PSA-3 CL-2 3RHS4PSSP0401 RH R Basic PSA PSA-3 CL-2 3RHS4PSSP0403 RHR Basic PSA PSA-3" CL-2 3RHS4PSSP0406 RHR Basic PSA PSA-10 CL-2 3RHS4PSSP0407 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0408 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0409 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0411 RHR Basic PSA PSA-1 CL-2 3RHS4PSSP0412 RHR Basic PSA PSA-1 CL-2 3RHS4PSSP0413 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0414 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0415 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0416 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0417 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0419 RHR Basic PSA PSA-1 CL-2 3RHS4PSSP0420 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0421 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0422 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0423 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0424 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0427 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0428 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0429 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0430 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0431 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0434 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0438 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0439 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0440 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0443 RHR Basic PSA PSA-1 CL-2 3RHS4PSSP0445 RHR Basic PSA PSA-1 CL-2 3RHS4PSSP0446 RHR Basic PSA PSA-1 CL-2 02/14/12 Date 02114112 RevO Page 20 of 28 Revision Date Rev 0 Page 20 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 10 of 13 Hanger ID Number System Manufacturer Size Class Note 3RHS4PSSP0447 RHR Basic PSA PSA-3 CL-2 3RHS4PSSP0448 RHR Basic PSA PSA-10 CL-2 3RHS4PSSP0449 RHR Basic PSA PSA-10 CL-2 3RHS4PSSP0454 RHR Basic PSA PSA-10 CL-2 3RHS4PSSP0459 RHR Basic PSA PSA-3 CL-2 3RSS4PSSP0406 CRS Basic PSA PSA-1 CL-2 3RSS4PSSP0407 CRS Basic PSA PSA-1 CL-2 3RSS4PSSP0408 CRS Basic PSA PSA-1 CL-2 3RSS4PSSP0409 CRS Basic PSA PSA-1 CL-2 3RSS4PSSP0410 CRS Basic PSA PSA-1 CL-2 3RSS4PSSP0411 CRS Basic PSA PSA-1 CL-2 3RSS4PSSP0415 CRS Basic PSA PSA-3 CL-2 3RSS4PSSP0417 CRS Basic PSA PSA-3 CL-2 3RSS4PSSP0459 CRS Basic PSA PSA-3 CL-2 3RSS4PSSP0460 CRS Basic PSA PSA-3 CL-2 3SIH1 PSSP0451 HPI Basic PSA PSA-1 CL-1 3SIHlPSSP0452 HPI Basic PSA PSA-1 CL-1 3SIHlPSSP0453 HPI Basic PSA PSA-3 CL-1 3SIHlPSSP0457 HPI Basic PSA PSA-10 CL-1 3SIHl PSSP0458 HPI Basic PSA PSA-3 CL-1 3SIHlPSSP0905 HPI Basic PSA PSA-3 CL-1 3SIHlPSSP1031 HPI Basic PSA PSA-1 CL-1 3SIHlPSSP1032 HPI Basic PSA PSA-1 CL-1 3SIH1PSSP1 109 HPI Basic PSA PSA-I CL-1 3SIH4PSSP0402 HPI Basic PSA PSA-3 CL-2 3SIH4PSSP0403 HPI Basic PSA PSA-1 CL-2 3SIH4PSSP0404 HPI Basic PSA PSA-1 CL-2 3SIH4PSSP0405 HPI Basic PSA PSA-1 CL-2 3SIH4PSSP0432 HPI Basic PSA PSA-1 CL-2 3SILl PSSP0400 LPI Basic PSA PSA-3 CL-2 3SILlPSSP0401 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0402 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0403 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0408 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0409 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP041 0 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0411 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0412 LPI Basic PSA PSA-1 CL-2 3SIL1 PSSP0413 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0414 LPI Basic PSA PSA-1 CL-2 3SIL1 PSSP0415 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0416 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0419 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0420 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0421 LPI Basic PSA PSA-3 CL-2 Rev 00 Page 21 of 28 Date 02/14/12 Revision Date 02114112 Rev Page 21 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 11 of 13 Hanger ID Number System Manufacturer Size Class Note 3SILl PSSP0422 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0423 LPI Basic PSA PSA-1 CL-2 3SIL1 PSSP0424 LPI Basic PSA PSA-1 CL-2 3SIL1 PSSP0425 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0426 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0427 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0428 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0429 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0430 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0431 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0436 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0437 LPI Basic PSA PSA-3 CL-2 3SILlPSSP0438 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0439 LPI Basic PSA PSA-'3 CL-2 3SIL1 PSSP0440 LPI Basic PSA PSA-1 CL-2 3SIL1 PSSP0441 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0442 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0443 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0444 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0445 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0448 LPI Basic PSA PSA-3 CL-2 3SILl PSSP0449 LPI Basic PSA PSA-10 CL-2 3SIL1 PSSP0451 LPI Basic PSA PSA-I CL-2 3SILl PSSP0452 LPI Basic PSA PSA-3 CL-2 3SILlPSSP0453 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0454 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0459 LPI Basic PSA PSA-1 CL-2 3SIL1 PSSP0462 LPI Basic PSA PSA-3 CL-1 3SIL1 PSSP0463 LPI Basic PSA PSA-3 CL-1 3SIL1 PSSP0464 LPI Basic PSA PSA-10 CL-1 3SIL1 PSSP0465 LPI Basic PSA PSA-3 CL-i 3SIL1 PSSP0466 LPI Basic PSA PSA-3 CL-i 3SIL1 PSSP0467 LPI Basic PSA PSA-3 CL-1 3SIL1 PSSP0468 LPI Basic PSA PSA-3 CL-1 3SIL1 PSSP0469 LPI Basic PSA PSA-10 CL-1 3SIL1 PSSP0470 LPI Basic PSA PSA-3 CL-1 3SIL1 PSSP0471 LPI Basic PSA PSA-3 CL-1 3SILl PSSP0472 LPI Basic PSA PSA-3 CL-1 3SILl PSSP0473 LPI Basic PSA PSA-3 CL-1 3SIL1 PSSP0903 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0904 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0907 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0908 LPI Basic PSA PSA-3 CL-2 3SIL1 PSSP0994 LPI Basic PSA PSA-3 CL-1 3SIL1 PSSP0995 LPI Basic PSA PSA-3 CL-1 Rev 00 Page 22 of 28 Date 02/1 Revision Date 4/12 02114112 Rev Page 22 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 12 of 13 Hanger ID Number System Manufacturer Size Class Note 3SIL1PSSP0996 LPI Basic PSA PSA-1 CL-I 3SIL1PSSP0997 LPI Basic PSA PSA-3 CL-1 3SILlPSSP0998 LPI Basic PSA PSA-3 CL-1 3SIL1PSSP0999 LPI Basic PSA PSA-3 CL-1 3SILlPSSP1000 LPI Basic PSA PSA-3 CL-2 3SIL1PSSP1001 LPI Basic PSA PSA-3 CL-2 3SILlPSSP1006 LPI Basic PSA PSA-1 CL-2 3SILlPSSP1007 LPI Basic PSA PSA-I CL-2 3SILlPSSP1034 LPI Basic PSA PSA-1 CL-1 3SIL1PSSP1036 LPI Basic PSA PSA-1 CL-2 3SIL1PSSP1042 LPI Basic PSA PSA-10 CL-2 3SILlPSSP1043 LPI Basic PSA PSA CL-2 3SILlPSSP1050 LPI Basic PSA PSA-3 CL-2 3SIL1PSSP1051 LPI Basic PSA PSA-3 CL-2 3SILlPSSP1054 LPI- Basic PSA PSA-1 CL-2 3SIL4PSSPOO04 LPI Basic PSA PSA-3 CL-2 3SIL4PSSPOO05 LPI Basic PSA PSA-3 CL-2 3SIL4PSSPOO06 LPI Basic PSA PSA-3 CL-2 3SIL4PSSPOO1 1 LPI Basic PSA PSA-1 CL-2 3SIL4PSSPOO12 LPI Basic PSA PSA-1 CL-2 3SIL4PSSPOO13 LPI Basic PSA PSA-3 CL-2 3SIL4PSSPOO14 LPI Basic PSA PSA-3 CL-2 3SIL4PSSPOO17 LPI Basic PSA PSA-1 CL-2 3SIL4PSSPOO18 LPI Basic PSA PSA-i CL-2 3SIL4PSSPOO70 LPI Basic PSA PSA-3 CL-2 3SIL4PSSPOO72 LPI Basic PSA PSA-3 CL-2 3SVV4PSSPOO04 HDS Basic PSA PSA-10 CL-3 3SVV4PSSPOO07 HDS Basic PSA PSA-3 CL-3 3SVV4PSSPOO09 HDS Basic PSA PSA-1 CL-3 3SVV4PSSPOO15 HDS Basic PSA PSA-10 CL-3 3SVV4PSSPOO18 HDS Basic PSA PSA-3 CL-3 3SVV4PSSPOO20 HDS Basic PSA PSA-1 CL-3 3SVV4PSSP0O29 HDS Basic PSA PSA-3 CL-3 3SVV4PSSPOO30 HDS Basic PSA PSA-3 CL-3 3SVV4PSSPOO31 HDS Basic PSA PSA-3 CL-3 3SVV4PSSPOO32 HDS Basic PSA PSA-1 CL-3 3SVV4PSSPOO34 HDS Basic PSA PSA-10 CL-3 3SVV4PSSPOO39 HDS Basic PSA PSA-3 CL-3 3SVV4PSSPOO41 HDS Basic PSA PSA-3 CL-3 3SVV4PSSPOO44 HDS Basic PSA PSA-3 CL-3 3SWP2PSSP0402 SWS Basic PSA PSA-10 CL-3 3SWP2PSSP0405 SWS Basic PSA PSA-10 CL-3 3SWP2PSSP0409 SWS Basic PSA PSA-10 CL-3 3SWP2PSSP0410 SWS Basic PSA PSA-10 CL-3 02/1 4/1 2 RevO Page 23 of 28 Date 02114112 Revision Date Rev 0 Page 23 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group) Pg 13 of 13 Hanger ID Number System Manufacturer Size Class Note 3SWP2PSSP0411 SWS Basic PSA PSA-10 CL-3 3SWP2PSSP0412 SWS Basic PSA PSA-10 CL-3 3SWP4PSSP0423 SWS Basic PSA PSA-3 CL-3 3SWP4PSSP0427 SWS Basic PSA PSA-3 CL-3 CP379706H022 RSS Basic PSA PSA-1 CL-2 CP379706H025 RSS Basic PSA PSA-1 CL-2 CP379707H022 RSS Basic PSA PSA-1 CL-2 CP379707H025 RSS Basic PSA PSA-1 CL-2 CP407011HOOl CVS Basic PSA PSA-1 CL-4 SIB CP407011H004 CVS Basic PSA PSA-1 CL-2 CP408051 H001 BDG Basic PSA PSA-1 CL-4 SIB Notes SIB Non-QA Snubbers which constitute the Seismic Interface Boundary are labeled as "SIB" and are required to be included in the Surveillance Program as required by Specification SP-ME-570.

QA-DF and SIB-DF Dual Function snubbers which are Pipe Supports/Rupture Restraints are labeled as QA-DF or SIB-DF and are required to be included in the Surveillance Program as required by Specification SP-ME-570.

Rev 00 Page 24 of 28 Reiision Date 02/14/12 Revision Date 02114112 Rev Page 24 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut, Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.3 DPTG C (Mechanical Snubber PSA size 35 and 100 Test Group) Pg 1 of 3 Hanger ID Number System Manufacturer Size Class Note 3BDG4PSSPOO46 BDG Basic PSA PSA-35 CL-4 SIB-DF 3BDG4PSSP0049 BDG Basic PSA PSA-35 CL-4 SIB-DF 3BDG4PSSPOO52 BDG Basic PSA PSA-35 CL-4 SIB-DF 3BDG4PSSPOO55 BDG Basic PSA PSA-35 CL-4 SIB-DF 3FWS1 PSSP0400 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0401 FWS Basic PSA PSA-1 00 CL-2 3FWS1 PSSP0405 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0406 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0407 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0408 FWS Basic PSA PSA-35 CL-2 3FWS1PSSP0409 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP041 0 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0411 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0412 FWS Basic PSA PSA-100 CL-2 3FWS1 PSSP0416 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0417 FWS Basic PSA PSA-35 CL-2 3FWS1PSSP0418 FWS Basic PSA PSA-35 CL-2 3FWS1PSSP0419 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0420 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0421 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0422 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0423 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0424 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0425 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0428 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0433 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0434 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0435 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0436 FWS Basic PSA PSA-35 CL-2 3FWS1 PSSP0439 FWS Basic PSA PSA-35 CL-2 3FWS4PSSPOO23 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS4PSSPOO24 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS4PSSPOO25 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS4PSSPOO26 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS4PSSP0200 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS4PSSP0201 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS4PSSP0202 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS4PSSP0203 FWS Basic PSA PSA-100 CL-2 QA-DF 3FWS5PSSP0444 FWS Basic PSA PSA-35 CL-4 SIB 3FWS5PSSP0449 FWS Basic PSA PSA-35 CL-4 SIB 3MSS1 PSSP0439 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0440 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0441 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0443 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0444 STG Basic PSA PSA-35 CL-2 Revision Date 02/14/12 Rev 0 Page 25 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.3 (cont)

DPTG C (Mechanical Snubber PSA size 35 and 100 Test Group) Pg 2 of 3 Hanger ID Number System Manufacturer Size Class Note 3MSSlPSSP0445 STG Basic PSA PSA-35 CL-2 3MSSlPSSP0446 STG Basic PSA PSA-100 CL-2 3MSSlPSSP0447 STG Basic PSA PSA-100 CL-2 3MSSl PSSP0448 STG Basic PSA PSA-100 CL-2 3MSS1 PSSP0449 STG Basic PSA PSA-35 CL-2 3MSSI PSSP0450 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0451 STG Basic PSA PSA-100 CL-2 3MSS1 PSSP0452 STG Basic PSA PSA-100 CL-2 3MSS1 PSSP0453 STG Basic PSA PSA-100 CL-2 3MSS1 PSSP0454 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0455 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0475 STG Basic PSA PSA-35 CL-2 3MSS1 PSSP0476 STG Basic PSA PSA-35 CL-2 3MSS4PSSP0400 STG Basic PSA PSA-100 CL-2 3MSS4PSSP0401 STG Basic PSA PSA-100 CL-2 3MSS4PSSP0403 STG Basic PSA PSA- 100 CL-2 3MSS4PSSP0404 STG Basic PSA PSA-100 CL-2 3MSS4PSSP0409 STG Basic PSA PSA-100 CL-2 3MSS4PSSP041 0 STG Basic PSA PSA-1 00 CL-2 3MSS4PSSP0415 STG Basic PSA PSA-100 CL-2 3MSS4PSSP0416 STG Basic PSA PSA-100 CL-2 3MSS5PSSP0402 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0405 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0406 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0407 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0408 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0411 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0412 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0417 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0419 STG Basic PSA PSA-35 CL-4 SIB 3MSS5PSSP0496 STG Basic PSA PSA-35 CL-4 SIB 3RCSl PSSP0400 RCS Basic PSA PSA-35 CL-1 3RCSlPSSP0401 RCS Basic PSA PSA-35 CL-1 3RCSlPSSP0407 RCS Basic PSA PSA-35 CL-1 3RCSlPSSP0502 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSlPSSP0503 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSlPSSP0504 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1PSSP0511 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0512 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0513 RCS Basic PSA PSA-100 CL QA-DF 3RCS1 PSSP0514 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0515 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0516 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0517 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0518 RCS Basic PSA PSA-100 CL-1 QA-DF 02/14/1 2 Rev 00 Page 26 of 28 Revision Date 02114172 Rev Page 26 of 28

U3-24-SNUB-BAPOI Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.3 (cont)

DPTG C (Mechanical Snubber PSA size 35 and 100 Test Group) Pg 3 of 3 Hanger ID Number System Manufacturer Size Class Note 3RCSlPSSP0519 RCS Basic PSA PSA- 100 CL-1 QA-DF 3RCSlPSSP0522 RCS Basic PSA PSA-35 CL-1 3RCSl PSSP0564 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSl PSSP0565 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0566 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0567 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSlPSSP0568 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSl PSSP0569 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0570 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCS1 PSSP0571 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSlPSSP0572 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSlPSSP0573 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSlPSSP0574 RCS Basic PSA PSA-100 CL-1 QA-DF 3RCSl PSSP0575 RCS Basic PSA PSA-100 CL-1 QA-DF 3RHSlPSSP0403 RHR Basic PSA PSA-35 CL-1 3RHSlPSSP0404 RHR Basic PSA PSA-35 CL-1 3RHS1PSSP0405 RHR Basic PSA PSA-35 CL-1 3RHS1PSSP0406 RHR Basic PSA PSA-35 CL-1 3RHS1 PSSP0412 RHR Basic PSA PSA-100 CL-1 3RHS1 PSSP0413 RHR Basic PSA PSA-35 CL-1 3SIL1 PSSP0474 LPI Basic PSA PSA-35 CL-1 QA-DF 3SIL1 PSSP0475 LPI Basic PSA PSA-35 CL-1 QA-DF 3SIL1 PSSP0476 LPI Basic PSA PSA-35 CL-1 QA-DF 3SILlPSSP0477 LPI Basic PSA PSA-35 CL-1 QA-DF 3SWP2PSSP0406 SWS Basic PSA PSA-100 CL-3 Notes SIB Non-QA Snubbers which constitute the Seismic Interface Boundary are labeled as "SIB" and are required to be included in the Surveillance Program as required by Specification SP-ME-570.

QA-DF and SIB-DF Dual Function snubbers which are Pipe Supports/Rupture Restraints are labeled as QA-DF or SIB-DF and are required to be included in the Surveillance Program as required by Specification SP-ME-570.

Rev 00 Page 27 of 28 Revision Date 021141122 Date 02/14/1 Rev Page 27 of 28

U3-24-SNUB-BAPO1 Dominion Nuclear Connecticut,Inc.

Millstone Power Station Unit 3 ATTACHMENT 9.4 DPTG D (Hydraulic Snubber SG and RCP Test Group) Pg 1 of I Hanger ID Number System Manufacturer Size Class Note 3RCS1SUP4-01 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-02 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-03 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-04 RCS Paul Munroe 2000Kip CL-1 3RCS1 SUP4-05 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-06 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-07 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-08 RCS Paul Munroe 2000Kip. CL-1 3RCS1SUP4-11 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-13 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-14 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-15 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-16 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-17 RCS Paul Munroe 2000Kip CL-i 3RCS1SUP4-18 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-19 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-20 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-21 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-22 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-23 RCS Paul Munroe 2000Kip CL-i 3RCS1SUP4-24 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-25 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-26 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-27 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-28 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-29 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-30 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-31 RCS Paul Munroe 2000Kip CL-i 3RCS1SUP4-32 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-33 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-34 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-35 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-36 RCS Paul Munroe 2000Kip CL-i 3RCS1SUP4-37 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-38 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-39 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-40 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-41 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-42 RCS Paul Munroe 2000Kip CL-i 3RCS1SUP4-43 RCS Paul Munroe 2000Kip CL-i 3RCS1SUP4-45 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-46 RCS Paul Munroe 2000Kip CL-1 3RCS1SUP4-47 RCS Paul Munroe 2000Kip CL-1 3RCSISUP4-48 RCS Paul Munroe 2000Kip CL-1 Rev 00 Page 28 of 28 Date 02/1 Revision Date 4/12 02114112 Rev I Page 28 of 28