ML13228A265

Independent Spent Fuel Storage Installations Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act & License Amendment Request

ML13228A265
Person / Time
Site:	Calvert Cliffs, Nine Mile Point, Ginna
Issue date:	08/14/2013
From:	Spina J Calvert Cliffs, Constellation Energy Nuclear Group, EDF Group, Nine Mile Point, Ginna
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML13228A262	List: ML13228A265
References
Download: ML13228A265 (21)

Text

SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 James A. Spina Office 410-470-5203 VP-Corporate Site Operations Fax 410-470-6305 E-mail: James.Spina@cengllc.com CENG,.

a pMnt venture of O C..wftefttout Et~w i-*eD 4%

August 14, 2013 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Calvert Cliffs Independent Spent Fuel Storage Installation Materials License No. SNM-2505 NRC Docket No. 72-8 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410 Nine Mile Point Independent Spent Fuel Storage Installation General License NRC Docket No. 72-1036 R. E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR- 18 NRC Docket Nos. 50-244 and 72-67 R. E. Ginna Independent Spent Fuel Storage Installation General License Docket No. 72-67 Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act and License Amendment Request

REFERENCE:

(a) EA-13-092, Order Designating an Interim Class of NRC-Licensed Facilities that are Eligible to Apply to the Commission for Authorization to Use the Authority Granted Under the Provisions of Section 161 a of the Atomic Energy Act of 1954, as Amended, dated June 5, 2013 Pursuant to Section 161A of the Atomic Energy Act, 42 U.S.C. 2201a, Constellation Energy Nuclear Group, LLC (CENG), on behalf of its U.S. Nuclear Regulatory Commission (NRC)-licensed subsidiary companies Calvert Cliffs Nuclear Power Plant, LLC, Nine Mile Point Nuclear Station, LLC and R. E.

Constellation Energy Nuclear Group, LLC 100 Constellation Way, Suite 200C, Baltimore, MD 21202 Upon removal of Attachment 1, this submittal Is not restricted tiL~

" R5

Document Control Desk August 14 2013 Page 2 Ginna Nuclear Power Plant, LLC, requests Commission authorization to use Section 161A preemption authority to permit the use of weapons, such as those discussed in Attachment (1), at Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (CCNPP), Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI), Nine Mile Point Nuclear Station, Units 1 and 2 (NMPNS) and R. E. Ginna Nuclear Power Plant (Ginna). The CENG facilities are within the interim class of facilities designated by the Commission in Reference (a) as eligible to apply for this authority. This letter is also a request that the licenses for the CENG nuclear facilities be amended to reflect this new authority.

Calvert Cliffs Nuclear Power Plant, LLC owns and operates CCNPP under Renewed Facility Operating Licenses DPR-53 and DPR-69. It also owns and operates the co-located specific license ISFSI under Materials License SNM-2505. Calvert Cliffs Nuclear Power Plant and the ISFSI are located in Lusby, Maryland. Nine Mile Point Nuclear Station, LLC owns and operates NMPNS under Renewed Facility Operating Licenses DPR-63 and NPF-69. NMPNS is located in Scriba, New York. R. E. Ginna Nuclear Power Plant, LLC owns and operates Ginna under Renewed Facility Operating License DPR-1 8. Ginna is located in Ontario, New York.

Attachment (1) provides the basis for this request and the information necessary to allow the NRC to make the required determinations under Section 161A. Attachment (1) contains security-related information and should be withheld from public disclosure pursuant to 10 CFR 2.390.

In accordance with the provisions of 10 CFR 50.90 and 72.56, and as required in Reference (a), CENG is requesting that the NRC amend the licenses of the CENG licensees to reflect this new authority.

Attachment (2) includes the required evaluation of the proposed changes to the licenses. As explained in Attachment (2), the proposed changes to the licenses have been evaluated in accordance with 10 CFR 50.91(a)(1) using the criteria in 10 CFR 50.92(c), and it has been determined that the changes involve no significant hazards considerations.

There are no regulatory commitments in this submittal.

Constellation Energy Nuclear Group requests approval of the license amendment request upon the NRC's issuance of a Confirmatory Order granting the requested authority. A 30-day implementation period from the date of approval is requested.

As required by 10 CFR 50.91(b), a copy of this request is being provided to the appropriate state representatives.

If there are any questions concerning this letter, please contact Everett (Chip) Perkins at everett.perkins(icengllc.com or 410-470-3928 I declare under penalty of perjury that the foregoing is true and correct. Executed on August 14, 2013.

Sincerely, JAS/EMT/bjd I

Document Control Desk August 14 2013 Page 3 Attachments: (1) Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act and License Amendment Request (2) Evaluation of Proposed Change cc: B. K. Vaidya, NRC M. C. Thadani, NRC N. S. Morgan, NRC W. M. Dean, NRC J. M. Goshen, NMSS C. Haney, NMSS Resident Inspector, Calvert Cliffs Resident Inspector, Ginna Resident Inspector, Nine Mile Point S. Gray, MD DNR A. L. Peterson, NYSERDA B. Frymire, NYSDPS

ATTACHMENT (2)

EVALUATION OF PROPOSED CHANGE TABLE OF CONTENTS 1.0

SUMMARY

DESCRIPTION 2.0 DETAILED DESCRIPTION

4.0 REGULATORY EVALUATION

4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA 4.2 SIGNIFICANT HAZARDS CONSIDERATION

4.3 CONCLUSION

S

Enclosures:

(2a) Proposed CCNPP, Unit 1 Facility Operating License Changes (markup)

(2b) Proposed CCNPP, Unit 2 Facility Operating License Changes (markup)

(2c) Proposed CCNPP ISFSI License Changes (markup)

(2d) Proposed NMPNS, Unit 1 Facility Operating License Changes (markup)

(2e) Proposed NMPNS, Unit 2 Facility Operating License Changes (markup)

(20 Proposed Ginna Facility Operating License Changes (markup)

Constellation Energy Nuclear Group, LLC August 14, 2013

ATTACHMENT (2)

EVALUATION OF PROPOSED CHANGE 1.0

SUMMARY

DESCRIPTION This evaluation supports a request to amend Operating Licenses DPR-53 and DPR-69 for Calvert Cliffs Nuclear Power Plant, Units 1 and 2; DPR-63 and NPF-69 for Nine Mile Point Nuclear Station, Units 1 and 2; DPR-18 for R.E. Ginna Nuclear Power Plant; and Material License SNM-2505 for the Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI).

The proposed changes would revise the operating and nuclear materials licenses to permit the use of Section 161A preemption authority under 42 U.S.C. 2201a, allowing the continued use at the nuclear facilities of the weapons discussed in Attachment (1) of the application and license amendment request letter.

2.0 DETAILED DESCRIPTION The Commission designated the facilities within the class of facilities eligible to apply for Section 161A preemption authority in EA- 13-092, Order Designatingan Interim Class of NRC-Licensed Facilitiesthat are Eligible to Apply to the Commission for Authorization to Use the Authority Granted Under the Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended, dated June 5, 2013.

EA-13-092 also specified that licensees must submit any application for Section 161A preemption authority as a license amendment request.

This license amendment request (LAR) proposes to add a sentence to the existing physical protection license condition in the operating licenses to reflect that the NRC has granted Section 161A preemption authority pursuant to the authority described in Section 161A of the Atomic Energy Act of 1954, as amended.

As set forth in Enclosures 2a-2f, and as required by EA-13-092, this LAR includes a proposed change to the existing license condition for physical protection for the facilities.

The following wording is proposed to be inserted into the physical protection license condition in the facilities licenses:

"The licensee has obtained Commission authorization to use Section 161A preemption authority under 42 U.S.C. 2201a for weapons at its facility."

3.0 TECHNICAL EVALUATION

The requested Section 161 A preemption authority is necessary for the armed security personnel at CENG nuclear facilities to perform their specific duties. Licensees are required under 10 CFR 73.55(b)(1) to establish and maintain a physical protection program, which includes a security organization and armed security personnel. To satisfy the general performance objective required in the regulations, a nuclear power plant's physical protection program must protect against the design basis threat (DBT) of radiological sabotage (10 CFR 73.1 and 10 CFR 73.55(b)(2)) and provide defense-in-depth (10 CFR 73.55(b)(3)(ii)). Specific physical protection program requirements for ISFSIs are also contained in 10 CFR Part 73, including in 10 CFR 73.5 1.

The physical protection programs for the nuclear facilities are contained in each facility's NRC-approved security plans, which for the reactors include the Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Cyber Security Plan, and for the Calvert Cliffs Nuclear Power Plant (CCNPP) ISFSI include the Physical Protection Plan. Obtaining Section 161A preemption authority I of4

ATTACHMENT (2)

EVALUATION OF PROPOSED CHANGE maintains the effectiveness of the security plans for the facilities, including the ability of their security forces to defend against the DBT and provide defense-in-depth.

4.0 REGULATORY EVALUATION

4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA This LAR is submitted pursuant to the order requirements provided in EA-13-092, the physical security requirements contained in 10 CFR Part 73, and the license amendment requirements in 10 CFR 50.90 and 72.56.

4.2 SIGNIFICANT HAZARDS CONSIDERATION Constellation Energy Nuclear Group, LLC (CENG), on behalf of the CENG Licensees, is submitting this license amendment request for Commission review and approval to recognize Commission authorization to use Section 161A preemption authority under 42 U.S.C. 2201a for weapons at CENG facilities. The following wording is proposed to be inserted into the physical protection license condition in the facilities licenses:

"The licensee has obtained Commission authorization to use Section 161A preemption authority under 42 U.S.C. 2201 a for weapons at its facility."

The proposed changes to the nuclear power plant licenses have been evaluated to determine whether a significant hazards consideration is involved with the proposed amendments by assessing the change using the three criteria of 10 CFR 50.92 as discussed below:

Criterion 1: Does the proposed change involve a significant increase in the probabilityor consequences ofan accidentpreviously evaluated?

Response: No The proposed change does not require any plant modifications, alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected.

The proposed change to the licenses will not result in any actual changes at the facilities. The security personnel already use the subject weapons and the use of the weapons is already covered under their existing security plans.

The proposed change adds a sentence to the operating licenses to reflect the Section 161 A preemption authority granted by the Commission. The change is administrative and has no impact on the probability or consequences of an accident previously evaluated. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2 of 4

ATTACHMENT (2)

EVALUATION OF PROPOSED CHANGE Criterion 2: Does the proposed change create the possibility of a new or different kind of accidentfrom any accidentpreviously evaluated?

Response: No The proposed change does not require any plant modifications, alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected.

The proposed change to the licenses will not result in any actual changes at the facilities. The security personnel already use the subject weapons and the use of the weapons is already covered under their existing security plans.

The proposed change adds a sentence to the operating licenses to reflect the Section 161 A preemption authority granted by the Commission. The change is administrative and has no impact on the possibility of a new or different kind of accident from any accident previously evaluated. Therefore, it is concluded that this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

Criterion3: Does the proposed change involve a significant reductionin a margin ofsafety.

The proposed change does not require any plant modifications, alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. Therefore, the implementation of the proposed change does not involve a significant reduction in a margin of safety.

The proposed change to the licenses will not result in any actual changes at the facilities. The security personnel already use the subject weapons and the use of the weapons is already covered under their existing security plans.

The proposed change to the license condition in the operating licenses adds a sentence to the existing license condition for physical protection to reflect the Section 161 A preemption authority granted by the Commission. The change is administrative and does not involve a significant reduction in a margin of safety. Therefore, the proposed change to the license conditions and the Commission granting the requested Section 161 A preemption authority does not create a significant reduction in a margin of safety.

Based on the above, the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of no significant hazards consideration is justified.

4.3 CONCLUSION

S 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.

3 of 4

ATTACHMENT (2)

EVALUATION OF PROPOSED CHANGE

5.0 ENVIRONMENTAL CONSIDERATION

The proposed amendment incorporates the Commission's Section 161A preemption authorization into the licensing basis for the CENG facilities. The weapons described in Attachment (1) are already in use by the security personnel and the use of the subject weapons is already covered under the existing security plans. For the nuclear plants, this proposed amendment will not involve (i) A significant hazardsconsideration, This is discussed in Section 4.2.

(ii) A significant change in the types or a significant increase in the amounts ofany effluents that may be releasedoffsite, or The proposed change adds a sentence to the operating licenses to reflect the Section 161A preemption authority granted by the Commission. The change is administrative and has no impact on release of effluents.

(iii) A significantincrease in individualor cumulative occupationalradiationexposure.

The proposed change adds a sentence to the operating licenses to reflect the Section 161A preemption authority granted by the Commission. The change is administrative and has no impact on occupational radiation exposure.

For the CCNPP ISFSI, this proposed amendment will not involve:

(i) A significantchange in the types or a significant increase in the amounts ofany effluents that may be released offsite, The proposed change adds a sentence to the operating license to reflect the Section 161A preemption authority granted by the Commission. The change is administrative and has no impact on release of effluents.

(ii) A significantincrease in individualor cumulative occupationalradiationexposure, The proposed change adds a sentence to the operating license to reflect the Section 161 A preemption authority granted by the Commission. The change is administrative and has no impact on occupational radiation exposure.

(iii) Significant construction impact, or The proposed change adds a sentence to the operating license to reflect the Section 161A preemption authority granted by the Commission. The change is administrative and has no impact on facility construction.

(iv) A significant increasein the potentialfor or consequencesfrom radiologicalaccidents.

The proposed change adds a sentence to the operating license to reflect the Section 161A preemption authority granted by the Commission. The change is administrative and has no impact on the potential for or consequences from radiological accidents.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (c)(11). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

4 of4

ENCLOSURE (2a)

Proposed CCNPP, Unit 1 Facility Operating License Changes (Markup)

Constellation Energy Nuclear Group, LLC August 14, 2013

c. Identification of process sampling points;

d. Procedure for recording and management of data;

e. Procedures defining corrective actions for off control point chemistry conditions; and

f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events required to initiate corrective action.

(5) Mitigation Strategy The Calvert Cliffs Nuclear Power Plant, LLC, shall develop and maintain strategies for addressing large fires and explosions that include the following key areas:

(a) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance

2. Assessment of mutual aid fire fighting assets

3. Designated staging areas for equipment and materials

4. Command and control

5. Training of response personnel (b) Operations to mitigate fuel damage considering the following:

1. Protection and use of personnel assets

2. Communications

3. Minimizing fire spread

4. Procedures for implementing integrated fire response strategy

5. Identification of readily available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures (c) Actions to minimize release to include consideration of:

1. Water spray scrubbing

2. Dose to onsite responders D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Calvert Cliffs Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 1" submitted May 19, 2006.

Amendment No. 295 I

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's 0 CSP was approved by License Amendment No. 298.

C E. The licensee shall implement and maintain in effect all provisions of the o approved fire protection program as described in the Updated Final Safety EC Analysis Report for the facility and as approved in the SER dated September 14, E 1979 and Supplements dated October 2, 1980; March 18, 1982; and CL September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: The licensee may make changes to the approved fire protection program without prior approval of the Commission only ifthose changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

0 F. At the time of the next scheduled update to the FSAR required pursuant to

_ 10 CFR 50.71 (e)(4) following the issuance of this renewed license, the licensee

._ shall update the FSAR to include the FSAR supplement submitted pursuant to M.* 10 CFR 54.21(d), as amended and supplemented by the program descriptions in 0 Appendix E to the Safety Evaluation Report, NUREG-1705. Until that FSAR update is complete, the licensee may make changes to the programs described in Appendix E without prior Commission approval, provided that the licensee o *evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 E* _ and otherwise complies with the requirements in that section.

E E m S, G. Any future actions listed in Appendix E to the Safety Evaluation Report, 0o NUREG-1 705, shall be included in the FSAR. The licensee shall complete these actions by July 31, 2014, except for the volumetric inspections of the control z0L element drive mechanisms, which must be completed no later than 2029 for Unit oW1 1 (Appendix E, Item 65).

0 H. This renewed license is effective as of the date of issuance and shall expire at midnight on July 31, 2034.

FOR THE NUCLEAR REGULATORY COMMISSION Samuel J. Collins, Director Office of Nuclear Reactor Regulation Attachments:

Appendix A - Technical Specifications Appendix B - Environmental Protection Plan (non-radiological) Technical Specifications Appendix C - Additional Conditions Date of Issuance: March 23, 2000 Amendment No. 298 1

ENCLOSURE (2b)

Proposed CCNPP, Unit 2 Facility Operating License Changes (Markup)

Constellation Energy Nuclear Group, LLC August 14, 2013

4. Procedures for implementing integrated fire response strategy

5. Identification of readily available pre-staged equipment

6. Training on integrated fire response strategy

7. Spent fuel pool mitigation measures C

(c) Actions to minimize release to include consideration of.

O

1. Water spray scrubbing

,o 2. Dose to onsite responders E D. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and CL safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR o 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: 'Calvert Cliffs Nuclear Power Plant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 1" submitted dated May 19, 2006.

0 Cp The licensee shall fully implement and maintain in effect all provisions of the o1 Commission-approved cyber security plan (CSP), including changes made

.1*

-4 pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was aproved by License Amendment No. 275.

c = E. The Calvert Cliffs Nuclear Power Plant, LLC, shall implement and maintain in

.o

• effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER E '* dated September 14, 1979, and Supplements dated October 2, 1980; March 18, a CAC 1982; and September 27, 1982; and Exemptions dated August 16, 1982; April 21, 1983; March 15, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: The Calvert Cliffs Nuclear Power Plant, LLC may make

.Z changes to the approved fire protection program without prior approval of the o ,Commission only if those changes would not adversely affect the ability to

- ,achieve and maintain safe shutdown in the event of a fire.

u F. At the time of the next scheduled update to the FSAR required pursuant to U (, 10 CFR 50.71(e)(4) following the issuance of this renewed license, the licensee shall update the FSAR to include the FSAR supplement submitted pursuant to

'- " 10 CFR 54.21(d), as amended and supplemented by the program descriptions in Appendix E to the Safety Evaluation Report, NUREG-1705. Until that FSAR update is complete, the licensee may make changes to the programs described in Appendix E without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G. Any future actions listed in Appendix E to the Safety Evaluation Report, NUREG-1 705, shall be included in the FSAR. The licensee shall complete these actions by August 13, 2016.

Amendment No. 275

ENCLOSURE (2c)

Proposed CCNPP ISFSI License Changes (Markup)

Constellation Energy Nuclear Group, LLC August 14, 2013

I NRC FORM 5A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 OF 4 PAGE 10 CFR 72 110-29M ~~~License No. Afxk* o LICENSE FOR INDEPENDENT STORAGE OF SPENT NUCLEAR SNM-2505 FUEL AND HIGH-LEVEL RADIOACTIVE WASTE Docket or Reference No. 72-8 SUPPLEMENTARY SHEET

12. The licensee shall fully implement and maintain in effect all provisions of the Independent Spent Fuel

• Storage Installation (ISFSI) physical security, guard training and qualification, and safeguards C contingency plans previously approved by the Commission and all amendments made pursuant to the . "

authority of 10 CFR 72.56, 10 CFR 72.44(e) and 72.186.

13. The Technical Specifications for Environmental Protection contained in Appendix A attached hereto are incorporated into the license. 0 Specifications required pursuant to 10 CFR 72.44(d), stating limits on the release of radioactive =

materials for compliance with limits of 10 CFR Part 20 and "as low as is reasonably achievable 0 objective" for effluents are not applicable. Dry Shielded Canister (DSC) external surface contamination within the limits of Technical Specification 3.2.3.1 ensures that the offsite dose will be inconsequential. .

In addition, there are no normal or off-normal releases or effluents expected from the double-sealed .

storage canisters of the ISFSI.

Specifications required pursuant to 10 CFR 72.44(dX1) for operating procedures, for control of effluents, "-

and for the maintenance and use of equipment in radioactive waste treatment systems to meet the N requirements of 10 CFR 72.104 are not applicable. There are, by the designof the sealed storage  %

canisters at the ISFSI, no effluent releases. Also, all Calvert Cliffs site DSC and Transfer Cask (TC) loading and unloading operations and waste treatment therefrom will occur at the Calvert Cliffs Nuclear 0 Power Plant under the specifications of its operating licenses.

14. No spent nuclear fuel shall be allowed to be loaded until such time as the following preoperational license conditions are satisfied: o

"-a A A training exercise (dry run) of all DSC, TC, and horizontal storage module (HSM) loading and handling activities shall be held and include but not be limited to, those listed below and -V need not be performed In the order listed:

1. Loading DSC in cask.

2. DSC (length may be truncated) drying, welding, and cover gas backfilling operations.

3. Moving cask to and aligning and docking with HSM on the storage pad. C

4. Insertion of DSC in HSM

5. Withdrawal of DSC from HSM

6. Returning the cask to the decontamination pit

7. Removing the cask lid and cutting open the DSC (length may be truncated) assuming fuel cladding failure.

8. Removing the DSC from the cask.

9. All dry run activities shall be done using written procedures.

10. The activities listed above shall be performed to show that each activity can be successfully executed prior to actual fuel loading.

ENCLOSURE (2d)

Proposed NMPNS, Unit 1 Facility Operating License Changes (Markup)

Constellation Energy Nuclear Group, LLC August 14, 2013

4-D. This license is subject to the following additional conditions:

(1) The licensee will complete construction of a new radwaste facility in conformance with the design defined and evaluated in the FES, to be operational no later than June 1976.

(2) Deleted by License Amendment No. 51

. (3) Deleted by License Amendment No. 51 r_ (4) Security. Trainina and Qualification and Safeauards Contingency Plans E-Ethe TheCommission-approved licensee shall fully implement physicaland maintain security, in effect training and allqualification, provisions of a,

C. and safeguards contingency plans, including amendments made pursuant to the provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and

_ to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined U* set of plans, which contain Safeguards Information protected under 10 CFR 73.21 is entitled "Nine Mile Point Nuclear Station, LLC Physical Security, Safeguards Contingency, and Security Training and 0 Qualification Plan, Revision 1,V and was submitted by letter dated

.- April 26, 2006.

The licensee shall fully implement and maintain in effect all provisions of O the Commission-approved cyber security plan (CSP), including changes

" made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

C -a The licensee's CSP was approved by License Amendment No. 209.

AA "

E :L- (5) Paragraph 2.D(5) of the license has been combined with paragraph E  % 2.D(4) as amended above into a single paragraph.

.~0 r (6) Recirculation System Safe-end Replacement 0o'0 The recirculation system and safe-end replacement program including

,M the cutting and welding of the replacement components and the dose mitigation program (ALARA) is approved, subject to the following A Nconditions:

a. The licensee shall complete the recirculation piping stress iE_,reanalysis prior to restart of Nine Mile Point Nuclear Power Station, Unit No. 1. The results of this analysis for selected representative portions of the recirculation system shall be submitted to the NRC prior to restart of the facility.

b. All fuel and control rods shall be removed from the reactor pressure vessel and stored in the spent fuel pool during the period that work on the safe-end and recirculation system replacement program is in progress.

Rnrew.d LWcen.. No. PPR-63 Roeced by 'ottr dAed Fentbuay 21, 209 Amendment No. 495, 209

ENCLOSURE (2e)

Proposed NMPNS, Unit 2 Facility Operating License Changes (Markup)

Constellation Energy Nuclear Group, LLC August 14, 2013

vi) A schedular exemption to 10 CFR 50.55a(h) for the Neutron Monitoring System until completion of the first refueling outage to allow the operating licensee to provide qualified isolation devices for Class 1 E/non-1 E interfaces described in their letters of June 23, 1987 (NMP2L 1057) and June 25, 1987 (NMP2L 1058). (Section 7.2.2.10, SSER 6).

For the schedular exemptions in iv), v), and vi), above, the operating licensee, in accordance with its letter of October 31, 1986, shall certify that all systems, components, and modifications have been completed to meet the requirements of the regulations for which the exemptions have been granted and shall provide a summary description of actions taken to ensure that the regulations have been met. This certification and summary shall be provided 10 days prior to the expiration of each exemption period as described above.

The exemptions set forth in this Section 2.0 are authorized by law, will not present an undue risk to public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the Safety Evaluation Report and the supplements thereto. The exemptions in ii)through vi) are granted pursuant to 10 CFR 50.12.

0

" With these exemptions, the facility will operate to the extent authorized herein, in C conformity with the application, as amended, the provisions of the Act, and the to rules and regulations of the Commission.

E

,t E. Nine Mile Point Nuclear Station, LLC shall fully implement and maintain in effect CL all provisions of the Commission-approved physical security, training and

<qualification, and safeguards contingency plans, including amendments made to pursuant to provisions of the Miscellaneous Amendments and Search

._ Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the tU authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21 is entitled "Nine Mile Point Nuclear Station, LLC Physical Security, Safeguards Contingency, and Security Training and Qualification Plan, Revision I,"and was 0o submitted by letter dated April 26, 2006. Changes made in accordance with 10

, CFR 73.55 shall be implemented in accordance with the schedule set forth 0 therein.

Nine Mile Point Nuclear Station, LLC shall fully implement and maintain in effect 0.M N all provisions of the Commission-approved cyber security plan (CSP), including Su.changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

E *The Nine Mile Point Nuclear Station's CSP was approved by License

.: 0 Amendment NQ. 137.

. 3, F. Nine Mile Point Nuclear Station, LLC shall implement and maintain in effect all

-0 ' provisions of the approved fire protection program as described in the Final mM Safety Analysis Report for the facility through Amendment No. 27 and as 0 described in submittals dated March 25, May 7 and 9, June 10 and 25. July 11 and 16, August 19 and 22, September 5, 12, and 23, October 10, 21, and 22,

. ,vi and December 9, 1986, and April 10 and May 20, 1987, and as approved in the cu :i SER dated February 1985 (and Supplements 1 through 6) subject to the Tr following provision:

Amendment 140 Issued by letter dated January 25, 2012

ENCLOSURE (20 Proposed Ginna Facility Operating License Changes (Markup)

Constellation Energy Nuclear Group, LLC August 14, 2013

I. C0 accordance with an acceptable calculational model which conforms to the provisions in Appendix K (SER dated April 18, 1978). The exemption will expire 0 upon receipt and approval of revised ECCS calculations. The aforementioned exemption is authorized by law and will not endanger life property or the common defense and security and is otherwise in the public interest. Therefore, the C exemption is hereby granted pursuant to 10 CFR 50.12.

.W E E. The licensee shall fully implement and maintain In effect all provisions of the Commission-approved physical security, training and qualification, end safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements C* revisions to 10 CFR 73.55 (51 FR 27827 and 27822) and to the authority of

.0 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains 1t Safeguards Information protected under 10 CFR 73.21, is entitled: "R. E. Ginna a) Nuclear Power Plant Security Plan, Training and Qualification Plan, and

,0 Safeguards Contingency Plan," submitted by letter dated May 15, 2006.

C

._2 The licensee shall fully Implement and maintain in effect all provisions of the

. Commission-approved cyber security plan (CSP), including changes made r4 pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's 0

o CSP was approved by Ucense Amendment No. 113.

0 U F. The Updated Final Safety Analysis Report supplement, submitted pursuant to 10 CFR 54.21 (d), describes certain future activities to be completed prior to the S*-period of extended operation. Ginna LLC shall complete these activities no later E

• than September 18, 2009, and shal notify the Commission In writing when implementation of these activities is complete and can be verified by NRC inspection.

M =The Updated Final Safety Analysis Report supplement, as revised, shall be included in the next scheduled update to the Updated Final Safety Analysis ol Report required by 10 CFR 50.71 (e)(4) following Issuance of this renewed Se4license. Until that update is complete, Ginna LLC may make changes to the u programs and activities descuibed in the supplement without prior Commission approval, provided that Ginna LLC evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

G. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of ASTM E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. Any capsules placed in storage must be maintained for future insertion, unless approved by the NRC.

Amendment No. 113