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. to this letter describes the proposed changes.

provides the marked-up TS pages. Marked-up TS Bases pages are provided in 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, 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, 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, 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, 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, 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, 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, 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, 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" shall mean

.nu.bbers 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 appa inprbe as a result. ofvisual inspections shall be classifieda 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 s-.

• espeIe T TTv [l~.4.^.-.-+

- L.- -..

.I.;.

Amendment No. 32, 6-2, 74,-2--

MILLSTONE - UNIT 3 3/47-22

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 THIS PAGE INTENTIONALLY LEFT BLANK 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-.

~Ait inspeetion ghall be pcrf4crmed of all snubbers attached to seefieons of systems thlat havo

.p r.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 +he pr-ior-test pcriod shall be implcm..tcd:

4 At 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*+ion 1.7.1 Of., an additional 5% of that Vfp1 of I.

.bber

.hal.

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 rld to

nbber.

fu-ancior.

may be dcferrcd until the end ofthe newt roftclintg whihever-is earlier-.

outage or-e 1ia: than Septemb*r-10, 1999,*

Amendment No. 6-2, 7, 4-00, 4-.

67 Th MILLSTONE - UNIT 3 3/4 7-23

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 have been tested;, or.

{

THIS PAGE INTENTIONALLY LEFT BLANK

-3)

A~n initial representative sample of 55 snubbers shall be functionally test 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 found which do not mneet the functional test aeceptancee criteriat. The rest 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 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.

d.

ed 9

S 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 Amendment No. i-& ýý MILLSTONE - UNIT 3 3/4 7-24

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

ký THIS PAGE INTENTIONALLY LEFT BLANK 3)

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 +he funcetional 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 4 A-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.

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 f.

art".. hall of r.,p÷la d

tat.. ton 4.......

during a p io.d wh en th e snubb..

replacamntes shall be daeumcnte acoordanco with Quality Assurar il

-A---ro tuositw itsery an~ iau maximum scriee life W~ill net be elfeedo is rogquirod to ho OPERAB~LE. T~ho parts d and +he docutmontiati shalil ho retained int icc ;roaratm +orietai Kcort.-

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

dnnuary r4-995-T-"6F4.E-74 SNU1BBER VISUAL INSPECTION INTEVAL NIJM-RFI1 gZ OFrr IN TTfl T rP 0444"pFRRZ peptilmion orf ttaegary (aeseee4-atd-4)

E*xtend int*ra l

Eiefeg-3-aftd-6)

Rcepem ne4eea (aeiee4 afld-6)

Roeduco Intcra (4e4oes 4ftvrd-6) 4-W0 0

4-4 440 0

4 4 400 2 400 8

4-8 436

-00 4-2 24 48

.4..

20 40 49 1 0arge-2.9

-56 4-09 Note 1:

'l%'vtlllij L

tLJ'JA Aa p

1 ev 1... iais p

'flA~iL.

iilr~~tenp zr 9zt 2mr Ai li

'i~II THIS PAGE INTENTIONALLY LEFT BLANK Noe e2!

Nate 4!

v a

c m1m~l*

.q b-,tlLU*.J

't...J 2

L vv T -- +

I. *

- L...

... 1

÷.

.4 +..

. I. *

. ÷

.1 basedpo thoi a sibit during powor oporation asacsible or :nreacossiblc.

T-hoccatogor-ics may bEcoamninod sepatreatly or joinitly. However, thaliccnisccmutst make and docuiment that dccision before any inspcction and shiall uisc that decision as thc basis.pon.which to dct.inc thcn i.....nsctin

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

.tcgo..

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 hoa b t'icc thc r-rcvious inton-al but+ i g~catcr lw 1k 8II may no tha if +th numb.. of una...ptable snubbcrs is cg.l to or losh

+than

.th numbr in Colu.mn B buti groator-than i~athonubor-in Column A, thc ncxt inspootion intcn'al shalil bo thce 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, q in.u Ium n 10ANK qý aM-

.L.

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

junudry 5 t-995

-AB16E.4.-2 SNUBER ISUA INPEC-TiON iNTTER-L Nate6-.

• 1 g

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 Amendment No. 6-2, 470 MILLSTONE - UNIT 3 3/4 7-28

-anarmy 3, t995 10 8

7 6

C5 4

3 2

1 I -

I -

I -

I -

I -

I -

I -

I -

I -

/

I I

I I

I I

I I

I

-f

/

UNATINUE TESNING

ýsssll CCEPIT S2030 405060 70 80 90 0

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

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

.CR.

05 MP3-025 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.d and 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,

IFor Information Only 4te 3, 32002 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 (nomina l.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 snubber-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 ree~etion sinlg t ritnQ*tvla P'n~iir~v 1

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.trial Sistic3" by A...

Wn 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.r life 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 ic.io odifians 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 a

pfmoatte 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, 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 Revised Snubber Program JsiiainfrCag equremnt.*:

Justification for 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, 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 Criteria Visual inspections shall verify that (1) the snubber has no visible indications of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are functional, and (3) fasteners for the attachment of the snubber to the component and to the snubber anchorage are functional.

ISTD-4210 states that inservice examination shall be a visual examination to identify physical damage, leakage, corrosion, or degradation that may have been caused by environmental exposure or operating conditions; and external characteristics that may indicate operational readiness of the snubber shall be examined.

ISTD-4231 requires that examinations shall include observations for the following and the conditions shall be evaluated when found:

(a) loose fasteners, or members that are corroded or deformed (b) disconnected components or other conditions that might interfere with the proper restraint of movement ISTD-4232 requires that examinations verify snubbers do not restrain thermal movement to an 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.

10 CFR 50.55a(b)(3)(v) allows the use of subsection ISTD for inservice examination requirements. Preservice and inservice examinations are required to be performed using the VT-3 visual examination method described in IWA-2213.

The revised snubber program requirements for inservice examination do not differ significantly from the visual inspection acceptance criteria in SR 4.7.10c.

For integral and non-integral attachments, the MPS3 ISI program will continue to meet the inspection requirements of ASME Section Xl, Article IWF-5200(c). The ISI program will be revised to include the inspection requirements of IWF-5300(c). See Commitment.

Serial No.12-036 Docket No. 50-423, 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)

Snubbers which appear inoperable as a result of visual inspections shall be classified as unacceptable and may be reclassified acceptable for the purpose of establishing the next visual inspection interval, provided that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers irrespective of type that may be generically susceptible; and (2) the affected snubber is functionally tested in the as-found condition and determined OPERABLE per Specification 4.7.10.f. All snubbers found connected to an inoperable common hydraulic fluid reservoir shall be counted as unacceptable for determining the next inspection interval. A review and evaluation shall be performed and documented to justify continued operation with an unacceptable snubber. If continued operation cannot be justified, the snubber shall be declared inoperable and the ACTION requirements shall be met.

ISTD-4240 permits snubbers classified as unacceptable during inservice examination to be tested in accordance with the requirements of ISTD-52 10. Results that satisfy the operational readiness test criteria of ISTD-5210 shall be used to accept the snubber, provided the test demonstrates that the unacceptable condition did not affect operational readiness.

ISTD-4233 requires that fluid supply or content for hydraulic snubbers shall be observed. If the fluid is less than the minimum amount, the installation shall be identified as unacceptable, unless a test establishes that the performance of the snubber is within specified limits. Tests shall be performed in accordance with ISTD-5210(b) and ISTD-5210(c). The initial test shall start with the piston at the as-found setting and be performed in the extension (tension) direction, or in a mode that more closely resembles the operating and design requirements of the snubber.

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.

The revised snubber program requirements for evaluation and corrective action for inservice examination are equivalent to those of current SR 4.7. Oc. for visual examination acceptance criteria.

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

Current TSSrveillance, Revise"d Snubber Program.

Justifiatio f Change ii~ qure.e"ht:,"! i.:il~:".ii eq ire en ii~ii:*'iiii~i:ii~'*:iiiil *.Justi.ficatiJu tiicaio : fror aneChange::::

~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, Page 6 of 12 Millstone Power Station Unit 3 Comparison of Current TS Surveillance Requirements to Revised Snubber Program Requirements (Continued)

'CurrentTS Surveillance Justification for Change Revised'snu bber Program.iiiii Jui 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, 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)

3) An initial representative sample of 55 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.

ISTD does not contain a 55 sample plan as an option.

The revised snubber program for MPS3 does not contain the 55 sample plan shown in the SR 4.7.1Oe.3.

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

Current TSSurveillance.

4 Revised Snubber Program T

Justification for Cha

'Reqjuirementj 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, 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 An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which may be subject to the same failure mode.

For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached. The purpose of this engineering evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the designed service.

If any snubber selected for functional testing either fails to lock up or fails to move, i.e.,

frozen-in-place, the cause will be evaluated and, if caused by manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated in Specification 4.7.10e. for snubbers not meeting the functional test acceptance criteria.

ISTD-5271 states that snubbers that do not meet test requirements shall be evaluated to determine the root cause of the failure.

ISTD-5272 states that snubbers found unacceptable according to operational readiness test requirements should be assigned to FMGs unless the failure is isolated or unexplained.

FMGs shall include all unacceptable snubbers with the same failure mode and all other snubbers with similar potential for similar failure.

ISTD-1800 requires that an evaluation shall be performed of the system(s) or components of which an unacceptable snubber is a part, for possible damage to the supported system or component.

As an alternative to additional testing for Design or Manufacturing FMGs, ISTD-5323 requires no additional testing when all snubbers in the FMGs are replaced or modified in accordance with ISTD-1 600. If replacement or modification is not performed in accordance with ISTD-5323, additional testing is required in accordance with ISTD 5324. Testing is required to continue until the acceptance limit is satisfied or all snubbers in the FMG have been tested.

The revised snubber program requirements for determining the cause of each failure for testing snubbers with the potential for similar failures are similar to.those of current SR 4.7.10g.

The revised snubber program requirements to evaluate the system(s) or components of an unacceptable snubber are equivalent to those of current SR 4.7.10g.

The revised program requirements for manufacturer or design deficiencies require replacement or modification of all snubbers in the FMG or additional testing until the mathematical expression of ISTD-5331(b) is satisfied or all snubbers in the FMG have been tested. This may result in fewer snubbers being tested after a test failure. However, the revised program requirements provide adequate assurance of snubber OPERABILITY because all potentially affected snubbers will be replaced or modified; or the acceptance limit for additional testing will be met, demonstrating an acceptable level of reliability.

.j. ________________________________

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

Current!TS Surveillance Revised SnubberlProgram T tification fo Chang Requirement',

Requirement I

4.7.1Oi. Snubber Service Life Program The service life of hydraulic and mechanical snubbers shall be monitored to ensure that the service life is not exceeded between surveillance inspections. The maximum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history.

Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the documentation shall be retained in accordance with Quality Assurance Program Topical Report.

ISTD-6100 requires initial snubber service life to be predicted based on manufacturer's recommendation or design review.

ISTD-6200 requires service life to be evaluated at least once each fuel cycle. If the evaluation indicates that service life will be exceeded before the next scheduled system or plant outage, one of the following actions shall be taken:

(a) the snubber shall be replaced with a snubber for which the service life will not be exceeded before the next scheduled system or plant outage (b) technical justification shall be 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 The service life evaluation requirements in ISTD-6100 and ISTD-6200 are equivalent to the requirements in current TS SR 4.7.1Oi.

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

Revision Date 02/1 4/12 Rev 0 Page 3 of 28 Revision Date 02114112 Rev 0 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, "General Requirements" 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 Nuclear Power 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.

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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 3BDG1 PSSP0406 3BDG1 PSSP0407 3BDG 1 PSSP0414 3BDG1 PSSP0417 3BDG1 PSSP0429 3BDG1 PSSP0430 3BDG1 PSSP0433 3BDG1 PSSP0487 3BDG1 PSSP0489 3BDG1 PSSP0491 3BDG1 PSSP0492 3BDGl PSSP0495 3BDG1 PSSP0496 3CHS1 PSSP0605 3CHS1PSSP0608 3CHS1PSSP0707 3CHS1 PSSP0718 3CHS1 PSSP0721 3CHS1 PSSP0726 3CHS1PSSP0727 3CHS1PSSP0728 3CHS1PSSP0740 3CHS1 PSSP0744 3CHS1 PSSP0992 3CHS1PSSP0993 3CHS1 PSSP1033 3CHS1PSSP1034 3CHS1PSSP1036 3CHS2PSSPO410 3CHS2PSSP0411 3CHS2PSSP0412 3CHS2PSSP0441 3CHS2PSSP0441 3CHS2PSSP0455 3CHS2PSSP0456 3CHS2PSSP0467 3CHS2PSSP0468 3CSS2 PSSP0456 3MSS1 PSSP0459 3MSS1 PSSP0460 3MSS1 PSSP0465 3MSS1 PSSP0466 3MSS1 PSSP0467 3MSS1 PSSP0471 3MSS1PSSP0472 System BDG BDG BDG BDG BDG BDG BDG BDG BDG BDG BDG BDG BDG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG CHG STG STG STG STG STG STG STG STG Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/4 Class CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-2.

CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-1 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 Note SIB SIB SIB SIB SIB SIB Revision Date 02/I 4/1 2 Rev 0 Page 7 of 28 Revision Date 02114112 Rev 0 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 3MSS4PSSPOO02 3MSS4PSSPO0O07 3MSS4PSSPOO1 1 3MSS4PSSP0O35 3MSS4PSSP0040 3MSS4PSSP0O42 3RCS11PSSP1520 3RCSl PSSP0027 3RCS1 PSSP0039 3RCSlPSSPOO44 3RCSl PSSP0046 3RCSlPSSP0106 3RCS1PSSP01 10 3RCS1 PSSP01 11 3RCS1 PSSPO113 3RCS1PSSPO0114 3RCSlPSSP0118 3RCStPSSP01 19 3RCSlPSSP0120 3RCSlPSSP0121 3RCSlPSSP0122 3RCSl PSSP0126 3RCS1PSSP0128 3RCS1PSSP0129 3RCSl PSSP0130 3RCSlPSSP0132 3RCSlPSSP0133 3RCSlPSSP0137 3RCSlPSSP0138 3RCSl PSSPO144 3RCSlPSSP0145 3RCSlPSSP0149 3RCSlPSSP0152 3RCSlPSSP0153 3RCSlPSSP0156 3RCSlPSSP0162 3RCSlPSSP0163 3RCSl PSSP0164 3RCSlPSSP0167 3RCS1PSSP0168 3RCS1PSSP0639 3RCS1 PSSP0729 3RCS1 PSSP0807 3RCS1 PSSP0913 3RCS1 PSSP0915 System STG STG STG STG STG STG RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 Class CL-3 CL-3 CL-3 CL-3 CL-3 CL-3 CL-2 CL-2 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 Note Revision Date 02/14/12 Rev 0 Page 8 of 28 Revision Date 02114112 Rev 0 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 3RCS1 PSSP0916 3RCS1 PSSP0917 3RCS1 PSSP0918 3RCSl PSSP0920 3RCS1PSSP0921 3RCS1PSSP0922 3RCS1PSSP0924 3RCS1PSSP0925 3RCS1 PSSP0926 3RCSl PSSP0928 3RCS1 PSSP0929 3RCS1PSSP0930 3RCSl PSSP0931 3RCS1 PSSP0932 3RCS1PSSP0937 3RCS1PSSP0938 3RCS1PSSP0939 3RCS1 PSSP0941 3RCS1PSSP0943 3RCS1 PSSP0945 3RCS1 PSSP0946 3RCS1 PSSP0959 3RCS1PSSP0962 3RCS1PSSP0963 3RCS1 PSSP0965 3RCS1PSSP0966 3RCS1 PSSP0967 3RCS1 PSSP0968 3RCS1PSSP0969 3RCS1PSSP0970 3RCS1 PSSP0971 3RCS1 PSSP0972 3RCS1PSSP0973 3RCSl PSSP0975 3RCS1 PSSP0976 3RCSl PSSP0977 3RCS1 PSSP0978 3RCS1 PSSP0979 3RCS1 PSSP0980 3RCS1 PSSP0981 3RCS1PSSP1018 3RCS1PSSP1019 3RCS1 PSSP1021 3RCS1PSSP1022 3RCSlPSSP1023 System RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1 /2 PSA-1 /4 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 Class CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-i CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-i CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-i CL-i Note Revision Date 02/1 4/12 Rev 0 Page 9 of 28 Revision Date 02114112 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 3RCS1PSSP1037 3RCSlPSSP1038 3RCS1PSSP1039 3RCSlPSSP1040 3RCS1 PSSP1041 3RCSiPSSP1045 3RCS1PSSP1063 3RCS1PSSP1 113 3RCS1 PSSP1 114 3RCSlPSSP1116 3RCS1 PSSP1 119 3RCS1 PSSP1 231 3RCSlPSSP1233 3RCSlPSSP1235 3RCSlPSSP1237 3RCSlVPSSP1517 3RCS1VPSSP1518 3RCS1VPSSP1522 3RCSlVPSSP1523 3RCSlVPSSP1524 3RCSlVPSSP1525 3RCSlVPSSP1526 3RCS1VPSSP1527 3RHS4PSSP0402 3RHS4PSSP0444 3SIHlPSSP0142 3SIH1PSSP0143 3SIH1PSSP0157 3SIHlPSSP0158 3SIHlPSSP0159 3SIHl PSSP0450 3SIHlPSSP1029 3SIH1PSSP1030 3SIHl PSSP1044 3SIH1PSSP1 102 3SIHi PSSP1 110 3SILlPSSP0450 3SILlPSSP1028 CP302760H004 CP302760H006 CP302760H010 CP302761 H004 CP302761HOO5 CP302761 H009 System RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RHR RHR HPI HPI HPI HPI HPI HPI HPI HPI HPI HPI HPI LPI LPI STG STG STG STG STG STG Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1 /2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1 /2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 Class CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL:I CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-2 CL-2 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-2 CL-2 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 Note SIB SIB SIB SIB SIB SIB Revision Date 02/1 4/12 Rev 0 Page 10of28 Revision Date 02114112

.Rev 0 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 1/22 Test Group)

Pg 5of 5 Hanger ID Number CP302762H001 CP302762H012 CP302763H004 CP302763H008 CP302763H012 CP371500HOOl CP394044H005 CP394045H001 CP394045H004 CP394045H005 CP394045H010 CP394052H001 CP394052H005 CP394052H006 CP394052H008 CP408051 H003 CP408051 H006 CP408052H003 CP408052H006 CP408053H003 CP408054H001 CP408054H003 CP408055H002 CP408056H001 CP408057H001 CP408057H002 CP408058H004 CP409004H006 CP409004H010 CP409005H010 CP409005H012 CP409005H013 CP409005H015 CP409701H009 CP409701 H01 6 System STG STG STG STG STG RHS DTM DTM DTM DTM DTM DTM DTM DTM DTM BDG BDG BDG BDG BDG BDG BDG BDG BDG BDG BDG BDG RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Basic PSA

,Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA BasicýPSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/4 PSA-1/2 PSA-1/4 PSA-1/4 PSA-1/4 Class CL-3 CL-3 CL-4 CL-4 CL-4 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-4 CL-4 CL-2 CL-2 CL-2 CL-2 Note SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB 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.

Revision Date 02/14/12 Rev 0 Page 11 of 28 Revision Date 02114172 Rev 0 Page I11 of 28

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

Millstone Power Station Unit 3 Hanger ID Numbei 3BDG1 PSSP0400 3BDG1 PSSP040i 3BDG 1 PSSP0402 3BDG1 PSSP0403 3BDG1 PSSP0404 3BDG1 PSSP0408 3BDG1 PSSP0409 3BDG1 PSSP0411 3BDG 1 PSSP0412 3BDG 1 PSSP0413 3BDG 1 PSSP0416 3BDG 1 PSSP0418 3BDG 1 PSSP0419 3BDG1 PSSP0420 3BDG1 PSSP0421 3BDG1 PSSP0422 3BDG1 PSSP0423 3BDG1 PSSP0424 3BDG1 PSSP0426 3BDG1 PSSP0427 3BDG1PSSP0428 3BDG 1 PSSP0431 3BDG1 PSSP0432 3BDG1 PSSP0461 3BDG1 PSSP0462 3BDG1 PSSP0463 3BDG1 PSSP0479 3BDG1 PSSP0480 3BDG1 PSSP0481 3BDG1 PSSP0483 3BDG1 PSSP0484 3BDG1 PSSP0485 3BDG1 PSSP0488 3BDG1 PSSP0493 3BDG1 PSSP0508 3BDG4PSSPOO47 3BDG4PSSPOO50 3BDG4PSSPOO53 3BDG4PSSPOO56 3BDG4PSSP0200 3BDG4PSSP0201 3BDG4PSSP0202 3BDG4PSSP0203 3CCP2PSSP0400 3CCP2PSSP0401 ATTACHMENT 9.2 DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group)

System Manufacturer Size Class BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1L CL-2 BDG Basic PSA PSA-1L CL-2 BDG Basic PSA PSA-1L CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 L CL-2 BDG Basic PSA PSA-1 L CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 L CL-2 BDG Basic PSA PSA-1 L CL-2 BDG Basic PSA PSA-1L CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 L CL-2 BDG Basic PSA PSA-1 L CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PsA-1 CL-4 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-1 CL-4 BDG Basic PSA PSA-1 CL-4 BDG Basic PSA PSA-1 CL-2 BDG Basic PSA PSA-10 CL-4 BDG Basic PSA PSA-10 CL-4 BDG Basic PSA PSA-10 CL-4 BDG Basic PSA PSA-10 CL-4 BDG Basic PSA PSA-10 CL-4 BDG Basic PSA PSA-10 CL-4 BDG Basic PSA PSA-10 CL-4 BDG Basic PSA PSA-10 CL-4 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 Pg 1 of 13 Note SIB SIB SIB SIB-DF SIB-DF SIB-DF SIB-DF SIB-DF SIB-DF SIB-DF SIB-DF Revision Date 02/14/12 Rev 0 Page 12 of 28 Revision Date 02114172 Rev 0 Page 12 of 28

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

Millstone Power Station Unit 3 Hanger ID Number 3CCP2PSSP0405 3CCP2PSSP0406 3CCP2PSSP0414 3CCP2PSSP0415 3CCP4PSSP0400 3CCP4PSSP0401 3CCP4PSSP0403 3CCP4PSSP0404 3CCP4PSSP0407 3CCP4PSSP0411 3CCP4PSSP0412 3CCP4PSSP0413 3CCP4PSSP0414 3CCP4PSSP0415 3CHS1PSSP0551 3CHS1PSSP0552 3CHS1 PSSP0610 3CHS1 PSSP0611 3CHS1 PSSP0613 3CHS1PSSP0626 3CHS1PSSP0635 3CHS1 PSSP0644 3CHS1PSSP0645 3CHS1PSSP0649 3CHS1PSSP0650 3CHS1 PSSP0653 3CHS1 PSSP0704 3CHS1PSSP0705 3CHS1 PSSP0706 3CHS1PSSP0711 3CHS1PSSP0712 3CHS1 PSSP0719 3CHS1 PSSP0720 3CHS1 PSSP0742 3CHS1PSSP1035 3CHS1PSSP1058 3CHS2PSSP0400 3CHS2PSSP0401 3CHS2PSSP0402 3CHS2PSSP0413 3CHS2PSSP0414 3CHS2PSSP0460 3CHS2PSSP0461 3CHS2PSSP0466 3DTM4PSSPOO27 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group)

System Manufacturer Size Class CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-10 CL-3 CCP Basic PSA PSA-10 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-10 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CCP Basic PSA PSA-3 CL-3 CHG Basic PSA PSA-10 CL-2 CHG Basic PSA PSA-10 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-i CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-1 CL-2 CHG Basic PSA PSA-3 CL-2 CHG Basic PSA PSA-3 CL-2 CHG Basic PSA PSA-3 CL-2 DTM Basic PSA PSA-1 CL-2 Pg 2 of 13.

Note QA-DF QA-DF Revision Date 02/I 4/1 2 Rev 0 Page 13 of 28 Revision Date 02114112 Rev 0 Page 13 of 28

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

Millstone Power Station Unit 3 Hanger ID Number 3DTM4PSSPOO30 3DTM4PSSPOO39 3DTM4PSSPOO42 3DTM4PSSPOO51 3DTM4PSSPOO54 3DTM4PSSPOO63 3DTM4PSSPOO66 3EGD6PSSPOO01 3EGD6PSSPOO03 3EGD6PSSPOO10 3EGD6PSSPOO13 3EGD6PSSPOO15 3EGD6PSSPOO22 3EGD6PSSPOO25 3EGD6PSSPOO26 3FWA1 PSSP0400 3FWA1 PSSP0401 3FWA1 PSSP0402 3FWA1 PSSP0403 3FWA1 PSSP0404 3FWA1 PSSP0405 3FWA1 PSSP0406 3FWA1 PSSP0407 3FWA1 PSSP0408 3FWA1 PSSP0409 3FWA1 PSSP041 0 3FWA1PSSP0411 3FWA1 PSSP0412 3FWA1 PSSP0413 3FWA1 PSSP0414 3FWA1 PSSP0415 3FWA1 PSSP0416 3FWA1 PSSP0417 3FWA1 PSSP0418 3FWA1 PSSP0419 3FWA1 PSSP0420 3FWA4PSSP0936 3FWS1 PSSP0402 3FWS1 PSSP0403 3FWS1 PSSP0404 3FWS1 PSSP0413 3FWS1 PSSP0414 3FWS1PSSP0415 3FWS1 PSSP0426 3FWS1 PSSP0427 ATTACHMENT 9.2 (cont)

DPTG B (Mechanical Snubber PSA size 1, 3, and 10 Test Group)

System Manufacturer Size Class DTM Basic PSA PSA-1 CL-2 DTM Basic PSA PSA-1 CL-2 DTM Basic PSA PSA-1 CL-2 DTM Basic PSA PSA-1 CL-2 DTM Basic PSA PSA-1 CL-2 DTM Basic PSA PSA-1 CL-2 DTM Basic PSA PSA-1 CL-2 DGN Basic PSA PSA-3 CL-3 DGN Basic PSA PSA-3 CL-3 DGN Basic PSA PSA-10 CL-4 DGN Basic PSA PSA-3 CL-3 DGN Basic PSA PSA-3 CL-3 DGN Basic PSA PSA-10 CL-4 DGN Basic PSA PSA-10 CL-4 DGN Basic PSA PSA-10 CL-4 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-1 CL-2 AFW Basic PSA PSA-3 CL-2 AFW Basic PSA PSA-3 CL-2 FWS Basic PSA PSA-10 CL-2 FWS Basic PSA PSA-10 CL-2 FWS Basic PSA PSA-10 CL-2 FWS Basic PSA PSA-10 CL-2 FWS Basic PSA PSA-10 CL-2 FWS Basic PSA PSA-10 CL-2 FWS Basic PSA PSA-10 CL-2 FWS Basic PSA PSA-10 CL-2 Pg 3 of 13 Note SIB SIB SIB SIB QA-DF Revision Date 02/I 4/i 2 RevO Page 14 of 28 Revision 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 3FWS1 PSSP0429 3FWS1 PSSP0430 3FWS1 PSSP0431 3FWS1 PSSP0432 3FWS1 PSSP0437 3FWS1 PSSP0438 3FWS1 PSSP0440 3FWS1 PSSP0441 3FWS1 PSSP0442 3FWS1 PSSP0443 3FWS1 PSSP0444 3FWS1 PSSP0445 3FWS4PSSP0401 3FWS4PSSP0402 3FWS4PSSP0403 3FWS4PSSP0404 31C11PSSPOO05 31C11PSSPOO06 3MSS1 PSSP0438 3MSS1 PSSP0442 3MSS1 PSSP0457 3MSS1 PSSP0458 3MSS1 PSSP0461 3MSS1 PSSP0462 3MSS1 PSSP0463 3MSS1 PSSP0464 3MSS1 PSSP0468 3MSS1 PSSP0469 3MSS1 PSSP0470 3MSS1 PSSP0473 3MSS1 PSSP0474 3MSS1 PSSP0555 3MSS1 PSSP0558 3MSS1 PSSP0559 3MSS4PSSPOO03 3MSS4PSSPOO06 3MSS4PSSPOO09 3MSS4PSSPOO13 3MSS4PSSPOO14 3MSS4PSSPOO17 3MSS4PSSPOO22 3MSS4PSSPOO23 3MSS4PSSPOO24 3MSS4PSSPOO26 3MSS4PSSPOO28 System FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS IMS IMS STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-10 PSA-10 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1L PSA-1L PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-1 PSA-1 PSA-3 PSA-3 PSA-I PSA-1 PSA-3 PSA-3 PSA-1 PSA-3 PSA_3' PSA-1 PSA-1 Class CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-3 CL-3 CL-3 CL-1 CL-1 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-3 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-3 Note Revision Date 02/14/12 Rev 0 Page 15 of 28 Revision Date 02114112 Rev 0 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 3MSS4PSSPOO37 3MSS4PSSPOO60 3MSS4PSSP0102 3MSS4PSSPO1 11 3MSS4PSSP01 13 3MSS4PSSP0122 3MSS4PSSP0482 3MSS4PSSP0483 3MSS4PSSP0484 3MSS4PSSP0485 3MSS4PSSP0486 3MSS4PSSP0487 3MSS4PSSP0488 3MSS4PSSP0489 3MSS4PSSP0490 3MSS4PSSP0491 3MSS4PSSP0492 3MSS4PSSP0493 3MSS4PSSP0494 3MSS4PSSP0495 3MSS5PSSP0413 3MSS5PSSP0414 3MSS5PSSP0418 3MSS5PSSP0497 3QSS1PSSP0142 3QSS1PSSP0400 3QSS1 PSSP0401 3QSSl PSSP0402 3QSS1 PSSP0403 3QSS1PSSP0404 3QSS1PSSP0405 30SS1PSSP0406 3Q.SS1PSSP0408 3QSS1PSSP0409 3QSS1 PSSP0410 3QSS1 PSSP0411 3QSS1PSSP0420 3QSS 1 PSSP0421 3QSS1PSSP0448 3QSS1 PSSP0449 3QSS1 PSSP0450 3QSS1PSSP0451 3QSS1PSSP0453 3QSS1PSSP0454 3QSS1 PSSP0459 System STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG ass ass ass QSS ass QSS ass Qss ass ass ass ass ass ass ass ass ass ass ass ass ass Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-3 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-10 PSA-3 PSA-3 PSA-3 PSA-10 PSA-10 PSA-10 Class CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-3 CL-3 CL-3 CL-3 CL-2 CL-2 CL-2 CL-2 CL-3 CL-3 CL-3 CL-3 CL-2 CL-4 CL-4 CL-4 CL-4 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 Note SIB SIB SIB SIB Revision Date 02/1 4/12 Rev 0 Page 16 of 28 Revision Date 02114112 Rev 0 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 3QSS1 PSSP0460 3QSSl PSSP0469 3QSS4PSSP0400 3QSS4PSSP0401 3RCS1 IPSSP1 519 3RCS1 PSSP0009 3RCSlPSS P0012 3RCSlPSSPOO14 3RCSlPSSPOO16 3RCSlPSSP0019 3RCS1 PSSP0021 3RCSl PSSPO022 3RCSl PSSP0032 3RCSlPSSP0035 3RCSlPSSP0055 3RCSlPSSPOO56 3RCSl PSSPOO58 3RCS1 PSSP0061 3RCS1 PSSP0062 3RCSl PSSPOO64 3RCSl PSSPOO65 3RCS1 PSSPOO80 3RCS1 PSSPOO81 3RCS1 PSSPOO82 3RCS1 PSSP0083 3RCSl PSSPOO84 3RCSl PSSPOO86 3RCSl PSSPOO87 3RCSlPSSPOO88 3RCS1PSSP0089 3RCS1 PSSP0090 3RCS1 PSSP0091 3RCSl PSSPOO92 3RCSl PSSPOO94 3RCSl PSSPOO95 3RCSl PSSPOO96 3RCSl PSSP0097 3RCSl PSSPOO98 3RCSl PSSPOO99 3RCSlPSSP0101 3RCSl PSSP0103 3RCSl PSSP0104 3RCSlPSSP0105 3RCSlPSSP0107 3RCSlPSSP0112 System ass ass ass ass RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-10 PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-1 PSA-1 PSA-3 PSA-3 PSA-1 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-10 PSA-10 PSA-3 PSA-3 PSA-3 PSA-10 PSA-10 PSA-3 PSA-3 PSA-10 PSA-10 PSA-10 PSA-10 PSA-10 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 Class CL-2 CL-2 CL-2 CL-2 CL-2 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-1 CL-1 Note SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB Rei'ision Date 02/1 4/12 RevO Page 17of28 Revision Date 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 3RCS1PSSP0116 3RCS1 PSSP01 17 3RCSlPSSP0125 3RCSlPSSP0134 3RCSlPSSP0146 3RCS1PSSP0147 3RCSlPSSP0150 3RCS1PSSP0155 3RCSlPSSP0165 3RCSlPSSP0166 3RCSl PSSP0445 3RCSlPSSP0446 3RCSlPSSP0447 3RCSl PSSP0460 3RCS1 PSSP0461 3RCSlPSSP0521 3RCSlPSSP0523 3RCS1PSSP0525 3RCSl PSSP0526 3RCSlPSSP0527 3RCSlPSSP0528 3RCSlPSSP0529 3RCSlPSSP0530 3RCSlPSSP0532 3RCSl PSSP0606 3RCSlPSSP0607 3RCSlPSSP0608 3RCSlPSSP0640 3RCSlPSSP0641 3RCSlPSSP0642 3RCS1 PSSP0643 3RCSl PSSP0646 3RCS1PSSP0647 3RCS1 PSSP0648 3RCS1 PSSP0804 3RCSl PSSP0806 3RCSl PSSP0809 3RCS1 PSSP0810 3RCS1 PSSP0811 3RCSlPSSP0812 3RCSlPSSP0813 3RCS1 PSSP0815 3RCS1 PSSP0816 3RCS1 PSSP0819 3RCSlPSSP0820 System RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-10 PSA-10 PSA-3 PSA-3 PSA-10 PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-1 PSA-3 Class CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-4 CL-4 CL-4 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 Note SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB Revision Date 02/1 4/12 RevO Page 18of28 Revision Date 02114112 Rev 0 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 3RCSlPSSP0821 3RCSlPSSPO822 3RCSl PSSP0824 3RCSlPSSP0825 3RCSlPSSP0827 3RCS1 PSSP0828 3RCS1PSSP0829 3RCSlPSSP0830 3RCS1 PSSP0831 3RCSl PSSP0832 3RCSlPSSP0834 3RCS1 PSSP0835 3RCS1PSSP0836 3RCS1PSSP0837 3RCSl PSSP0838 3RCSl PSSP0839 3RCSlPSSP0840 3RCSlPSSP0841 3RCSl PSSP0842 3RCSl PSSP0844 3RCSl PSSP0845 3RCSl PSSP0849 3RCS1 PSSP0851 3RCS1PSSP0855 3RCSl PSSP0859 3RCSlPSSP0914 3RCS1 PSSP0923 3RCSl PSSP0927 3RCSl PSSP0933 3RCSIPSSP0934 3RCS1 PSSP0935 3RCSlPSSP0936 3RCSl PSSP0947 3RCSl PSSP0948 3RCSl PSSP0992 3RCSl PSSP0993 3RCSl PSSP1009 3RCSlPSSP1010 3RCS1PSSPi1011 3RCS1PSSP1020 3RCS1PSSP1024 3RCS1PSSP1025 3RCSlPSSP1026 3RCSlPSSP1068 3RCSlPSSP1092 System RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-1 PSAK-1 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1L PSA-1L PSA-1L PSA-1L PSA-1L PSA-1 PSA-1 PSA-10 PSA-10 PSA-1L PSA-1L PSA-1L PSA-i PSA-1 PSA-1L PSA-3 PSA-1 PSA-3 Class CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-1 CL-1 CL-1 CL-1 CL-1 CL-4 CL-4 CL-4 CL-4 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-4 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-4 Note SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB QA-DF QA-DF SIB Revision Date 02/1 4/1 2 Rev 0 Page 19 of 28 Revision Date 02114112 Rev 0 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 3RCSlPSSP1093 3RCS1 PSSP1 117 3RHS1PSSP0402 3RHSlPSSP0408 3RHSlPSSP0409 3RHS1 PSSP041i0 3RHS1 PSSP0411 3RHS1 PSSP0414 3RHSl PSSP0420 3RHSlPSSP0421 3RHSiPSSP0423 3RHS1PSSP0424 3RHS4PSSPOO06 3RHS4PSSP0400 3RHS4PSSP0401 3RHS4PSSP0403 3RHS4PSSP0406 3RHS4PSSP0407 3RHS4PSSP0408 3RHS4PSSP0409 3RHS4PSSP0411 3RHS4PSSP0412 3RHS4PSSP0413 3RHS4PSSP0414 3RHS4PSSP0415 3RHS4PSSP0416 3RHS4PSSP0417 3RHS4PSSP0419 3RHS4PSSP0420 3RHS4PSSP0421 3RHS4PSSP0422 3RHS4PSSP0423 3RHS4PSSP0424 3RHS4PSSP0427 3RHS4PSSP0428 3RHS4PSSP0429 3RHS4PSSP0430 3RHS4PSSP0431 3RHS4PSSP0434 3RHS4PSSP0438 3RHS4PSSP0439 3RHS4PSSP0440 3RHS4PSSP0443 3RHS4PSSP0445 3RHS4PSSP0446 System RCS RCS RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RH R RH R RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR RHR Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PsA-3 PSA-1L PSA-10 PSA-3 PSA-3 PSA-10 PSA-10 PSA-3 PSA-10 PSA-10 PSA-3 PSA-10 PSA-10 PSA-3 PSA-3 PSA-3" PSA-10 PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-1 Class CL-4 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 Note SIB Revision Date 02/14/12 RevO Page 20 of 28 Revision Date 02114112 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 3RHS4PSSP0447 3RHS4PSSP0448 3RHS4PSSP0449 3RHS4PSSP0454 3RHS4PSSP0459 3RSS4PSSP0406 3RSS4PSSP0407 3RSS4PSSP0408 3RSS4PSSP0409 3RSS4PSSP0410 3RSS4PSSP0411 3RSS4PSSP0415 3RSS4PSSP0417 3RSS4PSSP0459 3RSS4PSSP0460 3SIH1 PSSP0451 3SIHlPSSP0452 3SIHlPSSP0453 3SIHlPSSP0457 3SIHl PSSP0458 3SIHlPSSP0905 3SIHlPSSP1031 3SIHlPSSP1032 3SIH1PSSP1 109 3SIH4PSSP0402 3SIH4PSSP0403 3SIH4PSSP0404 3SIH4PSSP0405 3SIH4PSSP0432 3SILl PSSP0400 3SILlPSSP0401 3SIL1 PSSP0402 3SILl PSSP0403 3SILl PSSP0408 3SILl PSSP0409 3SIL1 PSSP041 0 3SIL1 PSSP0411 3SIL1 PSSP0412 3SIL1 PSSP0413 3SIL1 PSSP0414 3SIL1 PSSP0415 3SIL1 PSSP0416 3SIL1 PSSP0419 3SIL1 PSSP0420 3SIL1 PSSP0421 System RHR RHR RHR RHR RHR CRS CRS CRS CRS CRS CRS CRS CRS CRS CRS HPI HPI HPI HPI HPI HPI HPI HPI HPI HPI HPI HPI HPI HPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-3 PSA-10 PSA-10 PSA-10 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-1 PSA-1 PSA-3 PSA-10 PSA-3 PSA-3 PSA-1 PSA-1 PSA-I PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-1 PSA-3 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 Class CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 Note Revision Date 02/14/12 Rev 0 Page 21 of 28 Revision Date 02114112 Rev 0 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 3SILl PSSP0422 3SIL1 PSSP0423 3SIL1 PSSP0424 3SIL1 PSSP0425 3SIL1 PSSP0426 3SIL1 PSSP0427 3SILl PSSP0428 3SIL1 PSSP0429 3SILl PSSP0430 3SIL1 PSSP0431 3SILl PSSP0436 3SIL1 PSSP0437 3SILlPSSP0438 3SILl PSSP0439 3SIL1 PSSP0440 3SIL1 PSSP0441 3SIL1 PSSP0442 3SIL1 PSSP0443 3SIL1 PSSP0444 3SILl PSSP0445 3SILl PSSP0448 3SILl PSSP0449 3SIL1 PSSP0451 3SILl PSSP0452 3SILlPSSP0453 3SIL1 PSSP0454 3SIL1 PSSP0459 3SIL1 PSSP0462 3SIL1 PSSP0463 3SIL1 PSSP0464 3SIL1 PSSP0465 3SIL1 PSSP0466 3SIL1 PSSP0467 3SIL1 PSSP0468 3SIL1 PSSP0469 3SIL1 PSSP0470 3SIL1 PSSP0471 3SILl PSSP0472 3SILl PSSP0473 3SIL1 PSSP0903 3SIL1 PSSP0904 3SIL1 PSSP0907 3SIL1 PSSP0908 3SIL1 PSSP0994 3SIL1 PSSP0995 System LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI LPI Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-3 PSA-1 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-'3 PSA-1 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-10 PSA-I PSA-3 PSA-3 PSA-3 PSA-1 PSA-3 PSA-3 PSA-10 PSA-3 PSA-3 PSA-3 PSA-3 PSA-10 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 Class CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-1 CL-1 CL-1 CL-i CL-i CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-2 CL-2 CL-2 CL-2 CL-1 CL-1 Note Revision Date 02/1 4/12 Rev 0 Page 22 of 28 Revision Date 02114112 Rev 0 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)

Hanger ID Number System Manufacturer Size Class 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 Pg 12 of 13 Note Revision Date 02/1 4/1 2 RevO Page 23 of 28 Revision Date 02114112 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 3SWP2PSSP0411 3SWP2PSSP0412 3SWP4PSSP0423 3SWP4PSSP0427 CP379706H022 CP379706H025 CP379707H022 CP379707H025 CP407011HOOl CP407011H004 CP408051 H001 System SWS SWS SWS SWS RSS RSS RSS RSS CVS CVS BDG Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-10 PSA-10 PSA-3 PSA-3 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 PSA-1 Class CL-3 CL-3 CL-3 CL-3 CL-2 CL-2 CL-2 CL-2 CL-4 CL-2 CL-4 Note SIB 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.

Reiision Date 02/14/12 Rev 0 Page 24 of 28 Revision Date 02114112 Rev 0 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 3BDG4PSSPOO46 3BDG4PSSP0049 3BDG4PSSPOO52 3BDG4PSSPOO55 3FWS1 PSSP0400 3FWS1 PSSP0401 3FWS1 PSSP0405 3FWS1 PSSP0406 3FWS1 PSSP0407 3FWS1 PSSP0408 3FWS1PSSP0409 3FWS1 PSSP041 0 3FWS1 PSSP0411 3FWS1 PSSP0412 3FWS1 PSSP0416 3FWS1 PSSP0417 3FWS1PSSP0418 3FWS1PSSP0419 3FWS1 PSSP0420 3FWS1 PSSP0421 3FWS1 PSSP0422 3FWS1 PSSP0423 3FWS1 PSSP0424 3FWS1 PSSP0425 3FWS1 PSSP0428 3FWS1 PSSP0433 3FWS1 PSSP0434 3FWS1 PSSP0435 3FWS1 PSSP0436 3FWS1 PSSP0439 3FWS4PSSPOO23 3FWS4PSSPOO24 3FWS4PSSPOO25 3FWS4PSSPOO26 3FWS4PSSP0200 3FWS4PSSP0201 3FWS4PSSP0202 3FWS4PSSP0203 3FWS5PSSP0444 3FWS5PSSP0449 3MSS1 PSSP0439 3MSS1 PSSP0440 3MSS1 PSSP0441 3MSS1 PSSP0443 3MSS1 PSSP0444 System BDG BDG BDG BDG FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS FWS STG STG STG STG STG Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-1 00 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-100 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 Class CL-4 CL-4 CL-4 CL-4 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-4 CL-4 CL-2 CL-2 CL-2 CL-2 CL-2 Note SIB-DF SIB-DF SIB-DF SIB-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF SIB SIB 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 3MSSlPSSP0445 3MSSlPSSP0446 3MSSlPSSP0447 3MSSl PSSP0448 3MSS1 PSSP0449 3MSSI PSSP0450 3MSS1 PSSP0451 3MSS1 PSSP0452 3MSS1 PSSP0453 3MSS1 PSSP0454 3MSS1 PSSP0455 3MSS1 PSSP0475 3MSS1 PSSP0476 3MSS4PSSP0400 3MSS4PSSP0401 3MSS4PSSP0403 3MSS4PSSP0404 3MSS4PSSP0409 3MSS4PSSP041 0 3MSS4PSSP0415 3MSS4PSSP0416 3MSS5PSSP0402 3MSS5PSSP0405 3MSS5PSSP0406 3MSS5PSSP0407 3MSS5PSSP0408 3MSS5PSSP0411 3MSS5PSSP0412 3MSS5PSSP0417 3MSS5PSSP0419 3MSS5PSSP0496 3RCSl PSSP0400 3RCSlPSSP0401 3RCSlPSSP0407 3RCSlPSSP0502 3RCSlPSSP0503 3RCSlPSSP0504 3RCS1PSSP0511 3RCS1 PSSP0512 3RCS1 PSSP0513 3RCS1 PSSP0514 3RCS1 PSSP0515 3RCS1 PSSP0516 3RCS1 PSSP0517 3RCS1 PSSP0518 System STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG STG RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-35 PSA-100 PSA-100 PSA-100 PSA-35 PSA-35 PSA-100 PSA-100 PSA-100 PSA-35 PSA-35 PSA-35 PSA-35 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-1 00 PSA-100 PSA-100 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 Class CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-2 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-4 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL CL-1 CL-1 CL-1 CL-1 CL-1 Note SIB SIB SIB SIB SIB SIB SIB SIB SIB SIB QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF Revision Date 02/14/1 2 Rev 0 Page 26 of 28 Revision Date 02114172 Rev 0 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 3RCSlPSSP0519 3RCSlPSSP0522 3RCSl PSSP0564 3RCSl PSSP0565 3RCS1 PSSP0566 3RCS1 PSSP0567 3RCSlPSSP0568 3RCSl PSSP0569 3RCS1 PSSP0570 3RCS1 PSSP0571 3RCSlPSSP0572 3RCSlPSSP0573 3RCSlPSSP0574 3RCSl PSSP0575 3RHSlPSSP0403 3RHSlPSSP0404 3RHS1PSSP0405 3RHS1PSSP0406 3RHS1 PSSP0412 3RHS1 PSSP0413 3SIL1 PSSP0474 3SIL1 PSSP0475 3SIL1 PSSP0476 3SILlPSSP0477 3SWP2PSSP0406 System RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RHR RHR RHR RHR RHR RHR LPI LPI LPI LPI SWS Manufacturer Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Basic PSA Size PSA-100 PSA-35 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-100 PSA-35 PSA-35 PSA-35 PSA-35 PSA-100 PSA-35 PSA-35 PSA-35 PSA-35 PSA-35 PSA-100 Class CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-3 Note QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF QA-DF 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.

Revision Date 02/14/1 2 Rev 0 Page 27 of 28 Revision Date 02114112 Rev 0 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 Note Hanger ID Number 3RCS1SUP4-01 3RCS1SUP4-02 3RCS1SUP4-03 3RCS1SUP4-04 3RCS1 SUP4-05 3RCS1SUP4-06 3RCS1SUP4-07 3RCS1SUP4-08 3RCS1SUP4-11 3RCS1SUP4-13 3RCS1SUP4-14 3RCS1SUP4-15 3RCS1SUP4-16 3RCS1SUP4-17 3RCS1SUP4-18 3RCS1SUP4-19 3RCS1SUP4-20 3RCS1SUP4-21 3RCS1SUP4-22 3RCS1SUP4-23 3RCS1SUP4-24 3RCS1SUP4-25 3RCS1SUP4-26 3RCS1SUP4-27 3RCS1SUP4-28 3RCS1SUP4-29 3RCS1SUP4-30 3RCS1SUP4-31 3RCS1SUP4-32 3RCS1SUP4-33 3RCS1SUP4-34 3RCS1SUP4-35 3RCS1SUP4-36 3RCS1SUP4-37 3RCS1SUP4-38 3RCS1SUP4-39 3RCS1SUP4-40 3RCS1SUP4-41 3RCS1SUP4-42 3RCS1SUP4-43 3RCS1SUP4-45 3RCS1SUP4-46 3RCS1SUP4-47 3RCSISUP4-48 System RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS RCS Manufacturer Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Paul Munroe Size 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip.

2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip 2000Kip Class CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-i CL-1 CL-1 CL-1 CL-1 CL-1 CL-i CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-1 CL-i CL-1 CL-1 CL-1 CL-1 CL-i CL-1 CL-1 CL-1 CL-1 CL-1 CL-i CL-i CL-1 CL-1 CL-1 CL-1 Revision Date 02/1 4/12 Rev 0 Page 28 of 28 Revision Date 02114112 Rev 0 I Page 28 of 28