ML14093A028

Millstone Power Station Unit 1 - License Amendment Request for Administrative Changes to the Permanently Defueled Technical Specifications

ML14093A028
Person / Time
Site:	Millstone
Issue date:	03/28/2014
From:	Sartain M D Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
14-035
Download: ML14093A028 (17)

Text

IV Dominioiiif Dominion Nuclear Connecticut, Inc.5000 Dominion Boulevard, Glen Allen, VA 23060Web Address:

www.dom.corn March 28, 2014U.S. Nuclear Regulatory Commission Attention:

Document Control DeskWashington, DC 20555Serial NoNSSL/MLCDocket No.License No.14-035RO50-245DPR-21DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT ILICENSE AMENDMENT REQUEST FOR ADMINISTRATIVE CHANGES TO THEPERMANENTLY DEFUELED TECHNICAL SPECIFICATIONS In accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) is submitting a license amendment request (LAR) to revise the Millstone Power Station Unit 1 (MPS1) Permanently Defueled Technical Specifications (PDTSs).

The proposed LAR deletes the Table of Contents section and makesadministrative changes to the PDTSs.Attachment 1 to this letter provides a description and evaluation of the proposedchanges.

Attachment 2 contains the marked-up PDTS pages of the proposedchanges.

The proposed changes do not involve a Significant HazardsConsideration under the standards set forth in 10 CFR 50.92. The Facility SafetyReview Committee has reviewed and concurred with the determinations herein.In accordance with 10 CFR 50.91(b),

a copy of this license amendment request isbeing provided to the State of Connecticut.

Should you have any questions in regard to this submittal, please contact WandaCraft at (804) 273-4687.

Sincerely, Mark D. SartainVice President

-Nuclear Engineering E VICKI L. HULLCommonwealth at Virginia140542MyCommission Expires May 31. 2014COMMONWEALTH OF VIRGINIACOUNTY OF HENRICOThe foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by MarkD. Sartain, who is Vice President

-Nuclear Engineering of Dominion Nuclear Connecticut, Inc. He has affirmed before methat he is duly authorized to execute and file the foregoing document in behalf of that company, and that the statements in thedocument are true to the best of his knowledge and belief.Acknowledged before me this 2 ~day of AAL.. , 2014.My Commission Expires:

LAA(3yaOli"

.c.&j 1tAONotary PublicA1Z.

Serial No: 14-035Docket No. 50-245Page 2 of 2Attachments:

1. Evaluation of Proposed License Amendment

2. Marked-Up Permanently Defueled Technical Specification PagesCommitments made in this letter: Nonecc: U.S. Nuclear Regulatory Commission Region I2100 Renaissance Blvd, Suite 100King of Prussia, PA 19406-2713 M. C. ThadaniProject Manager -Millstone Power StationU.S. Nuclear Regulatory Commission One White Flint North11555 Rockville PikeMail Stop 08 B 1Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power StationDirector, Radiation DivisionDepartment of Energy and Environmental Protection 79 Elm StreetHartford, CT 06106-5127 Serial No. 14-035Docket No. 50-245ATTACHMENT 1EVALUATION OF PROPOSED LICENSE AMENDMENT DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 1 Serial No. 14-035Docket No. 50-245Attachment 1, Page 1 of 5EVALUATION OF PROPOSED LICENSE AMENDMENT 1.0 SUMMARYIn accordance with the provisions of 10 CFR 50.90, Dominion Nuclear Connecticut, Inc.(DNC) is submitting a license amendment request (LAR) to revise the Millstone PowerStation Unit 1 (MPS1) Permanently Defueled Technical Specifications (PDTSs).

Theproposed LAR deletes the Table of Contents section and makes administrative changes tothe PDTSs.2.0 PROPOSED CHANGESDNC proposes to make the following changes to the MPS1 PDTSs:a) Delete the Table of Contents section from the PDTSs.b) Replace the position title of "assistant operations manager" in PDTS 5.3.2, FacilityStaff Qualifications, with "at least one operations middle manager."

c) Replace the term "SORG" on pages 5.0-7, 5.0-8, and 5.0-9 with the term "FSRC."Mark-ups of the affected PDTS pages for the proposed changes described above areprovided in Attachment 2.3.0 TECHNICAL EVALUATION The technical justification for each of the changes proposed in Section 2.0 of this LAR isprovided below:a) This LAR proposes to delete the Table of Contents section from the MPS1 PDTSs.Past LAR submittals to the NRC have included the Table of Contents section tosupport requested PDTS changes, and a revised Table of Contents has beenincluded in issued amendments.

This change will eliminate the need to includeTable of Contents pages as part of LAR submittals for future PDTS changes and toissue revised Table of Contents pages with an amendment.

Although the Table ofContents would no longer be considered part of the MPS1 PDTSs, controlled copyholders would continue to receive updates to the Table of Contents for future PDTSand PDTS Bases changes.The Table of Contents identifies the contents of the PDTSs and where the specificsections can be found but does not contain any technical information required by 10CFR 50.36. Therefore, this is an administrative change and does not involve anyphysical changes to structures,

systems, or components (SSCs) in the plant, or theway SSCs are operated or controlled.

Serial No. 14-035Docket No. 50-245Attachment 1, Page 2 of 5Similar amendments to remove the TS index were approved for Seabrook Station,Unit No. 1 in June 2013 (Reference 6.1), Waterford Unit 3 in May 2005 (Reference 6.2), and for Arkansas Nuclear One, Unit 2 in June 2005 (Reference 6.3).b) DNC proposes to revise PDTS 5.3.2, Facility Staff Qualifications, from:"The operations manager or assistant operations manager shall be a CERTIFIED FUEL HANDLER."

to:"The operations manager or at least one operations middle manager shall be aCERTIFIED FUEL HANDLER."

The proposed change replaces the position title of "assistant operations manager"with "at least one operations middle manager" and would require that either theoperations manager or at least one operations middle manager (e.g., an assistant operations manager or the supervisor in charge of the operations shift crews) be acertified fuel handler.

As discussed in the Regulatory Analysis section of this LAR(Section 4.1.2), the proposed change to PDTS 5.3.2 is administrative in nature andhas no technical implications on TS requirements.

The PDTSs will continue toprovide administrative controls relating to the organization and management ofMPS1 and to ensure compliance with regulations.

c) The term "SORC" which appears throughout the Administrative Controls section ofthe PDTSs, is no longer used at MPS. This acronym, which stood for SiteOperations Review Committee, has been replaced with FSRC or Facility SafetyReview Committee.

Consequently, the term "SORC" will be replaced with "FSRC."This proposed change is administrative in nature and does not involve any physicalchanges to SSCs in the plant, or the way SSCs are operated or controlled.

4.0 REGULATORY ANALYSIS4.1 Applicable Regulatory Requirements/Criteria 4.1.1 The NRC's regulatory requirements related to the content of the TSs are set forth inTitle 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications."

This regulation requires that the TSs include items in the following five specific categories:

(1) safety limits, limiting safety system settings, and limitingcontrol settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls.

However,the regulation does not specify the particular requirements to be included in aplant's TSs.

Serial No. 14-035Docket No. 50-245Attachment 1, Page 3 of 5The Table of Contents section which this LAR proposes to remove is not a requiredcomponent of the PDTSs in 10 CFR 50.36. Similar to the PDTS Bases, the Tableof Contents provides information about the PDTSs but is not part of the PDTSs.Because the Table of Contents section does not provide technical information required by 10 CFR 50.36, the proposed administrative change to remove the Tableof Contents section from the PDTSs is consistent with regulatory requirements.

4.1.2 PDTS 5.3.1 currently requires that each member of the facility staff shall meet orexceed the minimum qualifications of American National Standards Institute (ANSI)N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel,"

forcomparable positions.

This standard specifies that the operations manager hold anSRO license for the unit.By letter dated July 21, 1998, Northeast Nuclear Energy Company (NNECO)certified to the NRC, under the provisions of 10 CFR 50.82(a),

that MPS1 hadpermanently ceased operations and that the fuel had been permanently removedfrom the reactor vessel. Because licensed and senior licensed operators (SROs)were no longer required for a plant in a permanently defueled condition, the staffqualifications were modified (Reference 6.4) to require the operations manager orassistant operations manager to be a certified fuel handler.

This change ensuresthat the certified fuel handlers report to a management individual with at least anequivalent level of qualification.

DNC proposes to revise PDTS 5.3.2 such that the operations manager or at leastone operations middle manager shall be a certified fuel handler.

Modifying the titlein PDTS 5.3.2 to allow at least one operations middle manager (e.g., an assistant operations manager or the supervisor in charge of the operations shift crews) to bea certified fuel handler meets the intent of ANSI N18.1-1971.

This change will allowthe operations manager and other operations middle managers to perform higherlevel duties such as management,

planning, and coordinating of operations activities.

The proposed change will continue to meet the training and qualification requirements of 10 CFR 50.120 and the standards set forth in ANSI N18.1-1971 toensure there is relevant operational experience and knowledge in senior operations management position(s).

4.2 No Significant Hazards Consideration The NRC has provided standards for determining whether a significant hazardsconsideration exists as stated in 10 CFR 50.92(c).

A proposed amendment to anoperating license for a facility involves no significant hazards consideration if operation ofthe 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 accident previously evaluated; or 3) involve a significant reduction in a margin of safety.

Serial No. 14-035Docket No. 50-245Attachment 1, Page 4 of 5DNC has evaluated whether or not a significant hazards consideration is involved with theproposed changes.

A discussion of these standards as they relate to this change requestis provided below.1) Do the proposed changes involve a significant increase in the probability orconsequences of an accident previously evaluated?

Response:

No. The proposed changes are administrative in nature. The proposedchanges remove the PDTS Table of Contents section and make two otheradministrative changes to the PDTSs.Furthermore, MPS1 has permanently ceased operation and is being maintained ina defueled condition.

Therefore, the only credible design basis accident is a fuelhandling accident.

The administrative changes proposed herein are not initiators ofany fuel handling accident previously evaluated, and, consequently, the probability and consequences of a fuel handling accident previously evaluated is notsignificantly increased.

2) Do the proposed changes create the possibility of a new or different kind ofaccident from any accident previously evaluated?

Response:

No. The proposed changes are administrative in nature so no new ordifferent accidents result from the proposed changes.

The changes do not involvea physical alteration of the plant (i.e., no new or different type of equipment will beinstalled),

a change in the method of plant operation, or new operator actions.

Thechanges do not alter assumptions made in the safety analysis.

Therefore, theproposed changes do not create the possibility of a new or different kind of accidentfrom any previously evaluated.

3) Do the proposed changes involve a significant reduction in the margin ofsafety?Response:

No. The proposed administrative changes do not involve a change inthe method of plant operation, do not affect any accident

analyses, and do not relaxany safety system settings.

Therefore, the proposed changes do not involve asignificant reduction in a margin of safety.Based on the above, DNC concludes that the proposed changes do not present asignificant hazards consideration under the standards set forth in 10 CFR 50.92(c),

andaccordingly, a finding of "no significant hazards consideration" is justified.

4.3 Conclusion

Based on the considerations discussed above, (1) there is reasonable assurance that thehealth and safety of the public will not be endangered by operation in the proposedmanner, (2) such activities will be conducted in compliance with the Commission's Serial No. 14-035Docket No. 50-245Attachment 1, Page 5 of 5regulations, and (3) the issuance of the amendment will not be inimical to the commondefense and security or to the health and safety of the public.5.0 ENVIRONMENTAL CONSIDERATION DNC has determined that the proposed amendment would not change a requirement withrespect to installation or use of a facility component located within the restricted area, asdefined by 10 CFR 20, or an inspection or surveillance requirement.

The proposedamendment 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 bereleased

offsite, 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 CFR51.22(b),

no environmental impact statement or environmental assessment need to beprepared in connection with the proposed amendment.

6.0 REFERENCES

6.1 NRC Letter "Seabrook

Station, Unit No. 1 -Issuance of Amendment Regarding theAdministrative Changes and Corrections to the Technical Specifications (TAC No.MF1033),"

June 17, 2013 (ADAMS Accession No. ML13074A760).

6.2 NRC Letter "Waterford Steam Electric

Station, Unit 3 -Issuance of Amendment Re:Modification of Technical Specification (TS) 5.3.1, Fuel Assemblies, T.S. 5.6.1,Criticality, T.S. 6.9.1.11.1, Core Operating Limits Reports, and Deletion of TS Index(TAC No. MC3584),"

May 9, 2005 (ADAMS Accession No. ML051290368).

6.3 NRC Letter "Arkansas Nuclear One, Unit 2 -Issuance of Amendments Re: Deletionof Index Pages from the Technical Specifications (TAC No. MC3246),"

June 22,2005 (ADAMS Accession No. ML051740191).

6.4 NRC Letter "Issuance of Amendment No. 104 to Facility Olperating License No.DPR-21, Millstone Nuclear Power Station, Unit I(TAC No. MA4373),

March 5,1999.

Serial No. 14-035Docket No. 50-245ATTACHMENT 2MARKED-UP PERMANENTLY DEFUELED TECHNICAL SPECIFICATION PAGESDOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT I Serial No. 14-035Docket No. 50-245Attachment 2, Page 1 of 8March 44, 2094TABLE 012 OF COTN2T-SEGUOLPAQE.e..:..................

..................

.......................

..................

..................

4,4 OilJECATIVE................

...............

........

..........

I........

1:....1-,4 D EINITIONS.

.........

.-.... I ...................................

IneW -*m ant o.............

C .............

.............................

1-241 IMOfRurnzn or QBHannI FUnedfflal TeOt ..........................

1 2-I -"4 INtR-.M.

C.. zz.k ... ..............

.................

.......i 21.2.4 SI gg rzd Teat EB a is ................................................................................

1 2DELETED .....................

......................................................................

2 12-.Q^V4.0 ?j s! i We ater. im psaPrc e ...............................................................................

~4943M423M44ACTION..................................................1 A ETIO N ......................................................................................................

3/14 1SURVEILLANGE REQU'IM MEW' ...............................................................

M/41B A SE .........................................................

.I 4.4.... .. .hnsp eti. n ...........................................................................................................

5 1-I CTIO .. ....................................

.......................................................

5 154 M2C U ' ..................................................

EREN CE............................................

5 2M, LIWMIThG CONDITION FOR OPERATION..........

I ..........................

5.AC T IO N ... ..................................................................................................

.i-54 SURVEILL.ANCE REQUIREMENT................................................

52A in p otia .......................................................................................

5 2B T am ing.........................

...................................................................

5 2G speziaI R epeft ............................................

5 2-&6 A sup...........................................................

Io4-4-.OOlI Serial No. 14-035Docket No. 50-245Attachment 2, Page 2 of 8Mhafehh ! , 20 4TABLE OF CONTENTS (Ccntinud)

EAQE60 Fire Pretwzien Systems .........................................................................

616ý" O B JEC TIV E .......................................................................................

6 I6-.0.2 INDEX OF CONTENTS S.....................................................

6 164 BASES .................................................

6 16 0. 4 D) Afi1 U ' e ....................

vi...........................................................................

6 264-6 Administrative Requiremnents.................................................

6 2-64 FIRE SUPPRESSION WATER SYSTEM ................................................................

6 36.44 .........

C.N.TIONFOR.O.R.T.O..................

6364A APPLICABIT I .T"........................

...........

6364- ACTIOM ..... .................................................................

6 364A4 SURVEILLANCE

............................................................

6 -364-A BASES .........................................................................

6 36-. DELETED ......I............................................................................

6 764 DELETED .........................................

i.........................................

6264 -FIRE NOSER- SRT.ATIONS

.................................................................

6 964.4 LIMIT-ING CONDITON FOR OPERATION

.............................

6964-2 APPLICABILITY

............................................................

6 96A-3 ACTION .......................................................................

6 96-44 SURVEILLANCE.............................................................6 9644 BASES .......................................................................

.6 10M~illstone Unit A, inlatp Mrt tptps I Serial No. 14-035Docket No. 50-245Attachment 2, Page 3 of 8TABaLh 1ON, 209C260...i... ...............

....................................................................

......6 116 .12 APLC...................

............................................

6 6H6 A C TIO N ................................................................................................

6- 16 4 SURVE.LLANCE

.............................................................................

6 116,64 LIMITIN!G GOND)ITION FOR OPEFATION............................

61-36.44 APPLICABILITY

........................................................

6136 " A C O ...............................................................................................

6 13644A SLWEILLANCE

....... i...i.......

.....11-.11...m......................

.6 BA S S .- ............................................................................................

6 14PENETRATION FIRE BARRIERS

...................................................................

.1545176-446-.7-.36INIT4ING COND'FORP TO41 .................

OR TI.................6 15rtr-ýInix7n" M t-t-Ir .................................................

I .............................

.45ftk- 11 i'd ................................................................................................

6 is E ...........................................................................

6 15BASES ................................................

6 16ieffle i blcUbi Mdpi Wr ftldbis a~ itiN ilp ..........

1......i........0i Table2 FIRE DOORS ......................................

Tabl4 FIRE DETECTION INSTRUMENTS

.61.........I............

9Ho4 -M, 0oI Serial No. 14-035Docket No. 50-245Attachment 2, Page 4 of 8Mefeh 1, 044TABJLES Or. CONENT I (riG~twnuMe 9RIT4LE&GEMUnit I O JE I ThAt i .it .a .W i .h Un .t 2 M. 3 7........................

.............................................

7.......EC.IVE .1 .....I...............

... ....... I.................................7...

E FS ...........................................

.................................

................

7-7-. ME Fi11 IDRR "W G,- ..................................................

LIMITING CONDITION FOR OPERATION

.........

I.............................

7 3-A C T IO N ..........................................................................................................

7 3S E L L A C E ... ............................................

.......................................

7 3B A S E S .............................................................

..................................................

7 3Tanble I UNITr I S t TE.T SUPPOR T/IJIT 2FTIrT"ION OR LICENSE BASIS .. 7 sTable 2 DELETED..............................

I................................

7I-l rkrI -OC. T~YA'C F-ld'n T MTT- 1 .1 MTKIýT^

--Jb i .I .............

.... ...........

... ... ..

eaeUf-tu444-P0 4-04 MPI 001 1 Serial No. 14-035Docket No. 50-245Attachment 2, Page 5 of 8geptembor 15, 2005Facility Staff Qualifications 5.3ADMINISTRATIVE CONTROLS5.3 Facility Staff Qualifications 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.

Exceptions to this requirement arespecified in the Quality Assurance Program.5.3.2 The operations manager or _ccitant pr n aqwc rn_.gr shall be a CERTIFIED FUEL HANDLER.lat least one operations middle managerMILLSTONE-UNIT 15.0-5Amendment No. -, 404-4-,4-4 Serial No. 14-035Docket No. 50-245Attachment 2, Page 6 of 8BeptombeFr 17, 2002Procedures 5.55.0 ADMINISTRATIVE CONTROLS5.5 Procedures 5.5.1 Written procedures shall be established, implemented, and maintained coveringthe following activities:

a. The procedures applicable to the safe storage of irradiated fuelrecommended in Appendix "A" of Regulatory Guide 1.33, February 1978;b. Fire Protection Program implementation;

c. Cold Weather Operations;

d. Quality Controls for effluent monitoring, using the guidance in Regulatory LGuide 1.21, Rev. 1, June 1974; +-e. Liquid and gaseous radioactive effluent discharges from the unit for alloperations involving offsite releases of radioactive effluents.

Theseprocedures shall specify the use of appropriate waste treatment utilizing the guidance provided in the REMODCM;f. Fuel handling operations;

g. All programs specified in Specification 5.6, except for Section I.E.,Radiological Environmental Monitoring of REMODCM, which is performed in accordance with Specifications 5.5.6 and 5.5.7.5.5.2 The designated

manager, designated

officer, or designated senior officer maydesignate specific procedures and programs, or classes of procedures andprograms to be reviewed in accordance with the Station Qualified ReviewerProgram in lieu of review by the SORG. The review per the SORG or StationQualified Reviewer Program shall be accordance with .Quality Assurance Program Topical Report. FS.RC5.5.3 Procedures listed in Specification 5.5.1, and changes thereto, shall be approvedby the designated

manager, or designated officer or by cognizant managers ordirectors who are designated as the Approval Authority by the designated

manager, or designated officer as specified in administrative procedures.

TheApproval Authority foreach procedure and program or class of procedure andprogram shall be specified in administrative procedures.

(continued)

Millstone

-Unit 15.0-7Amendment No. 4.Q6, 4.-8, 4-44 Serial No. 14-035Docket No. 50-245Attachment 2, Page 7 of 8S-ptombor 1 7, 2902Procedures 5.55.0 ADMINISTRATIVE CONTROLS5.5 Procedures (continued) 5.5.4 Each procedure of Specification 5.5.1, and changes thereto, shall be reviewed by Lthe SOQRG .d shall be approved by the designated manager or designated

officer, 1or be revie nda approved in accordance with the Station Qualified ReviewerProgram prior to im etation.

Each procedure of Specification 5.5.1 shall bereviewed periodically as se hi amnistrative procedures.

5.5.5 Temporary changes to procedures of cain551aoemy be madeprovided:

a. the intent of the original procedure is not altered,i/b. the change is approved by two members of the plant m a~fgement staff, atleast one of whom is a CERTIFIED FUEL HANDLERj#

c. the change is documented, reviewed by the SQR or the Station Qualified Reviewer

Program, as applicable, and approved by the designated

manager, designated

officer, or the Station Qualified Reviewer Programdepartment manager within 14 days of implementation.

5.5.6 All procedures and procedure changes required for the Radiological Environmental Monitoring Program (REMP) of Specification 5.6.1 shall be reviewed by anindividual (other than the author) from the organization responsible for the REMPand approved by appropriate supervision.

5.5.7 Temporary changes may be made for the Radiological Environmental Monitoring Program provided the intent of the original procedure is not altered and the changeis documented and reviewed by an individual (other than the author) from the I_organization responsible for the REMP within 14 days of implementation."

(continued)

Millstone

-Unit I5.0-8Amendment No. 4--6, 444-Serial No. 14-035Docket No. 50-245Attachment 2, Page 8 of 8....9. Q ....Programs and Manuals5.65.0 ADMINISTRATIVE CONTROLS5.6 Programs and ManualsThe following programs shall be established, implemented and maintained.

5.6.1 Radioloaical Effluent Monitoring and Offsite Dose Calculation Manuala. The REMODCM shall contain the methodology and parameters used in thecalculation of offsite doses resulting from radioactive gaseous and liquideffluents, in the calculation of gaseous and liquid effluent monitoring alarmand trip setpoints, and in the conduct of the radiological environmental monitoring program; andb. The REMODCM shall also contain the radioactive effluent controls andradiological environmental monitoring activities and descriptions of theinformation that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent

Release, reportsrequired by Specification 5.7.2 and Specification 5.7.3.Licensee initiated changes to the REMODCM:a. Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:1) sufficient information to support the change(s) together with theappropriate analyses or evaluations justifying the change(s),

and2) a. determination that the change(s) will maintain the level ofradioactive effluent control required by 1 OCFR20.1302, 40CFR Part190, 10 CFR 50.36a and Appendix I to 1 OCFR50, and not adversely impact the accuracy or reliability of effluent,

.dose, or setpointcalculations;

b. Shall become effective after review and acceptance by &QQ and theapproval of the designated officer; and(continued)

Millstone

-Unit 15.0-9Amendment No. 446