ML082760384

Attachment 2, Marked Up Tech Spec Pages for License Amendment Request: Reporting of Reactor Vessel In-Service Inspection Information and Analyses in Support of Code Relief Request for Extension of Reactor Vessel

ML082760384
Person / Time
Site:	Calvert Cliffs
Issue date:	10/01/2008
From:	Calvert Cliffs, Constellation Energy Group, Nuclear Generation Group
To:	Office of Nuclear Reactor Regulation
Shared Package
ML082760380	List: ML082760382 ML082760383 ML082760384
References
TAC MC9768
Download: ML082760384 (4)

Text

ATTACHMENT (2)

MARKED UP TECHNICAL SPECIFICATION PAGES Renewed Operating License Page 4 (Unit 1)

Renewed Operating License Page 5 (Unit 2)

Calvert Cliffs Nuclear Power Plant, Inc.

October 1, 2008 c.

Identification of process sampling points; I

d.

Proce9ure for recording and management of data; i

e.

Procedures defining corrective actions for off control point chemistry conditions; and 1

I 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.

i (5).

Mitigation Strategy I

The Calvert d liffs Nuclear Power Plant, Inc., shall develop and maintain strategies for ~ddress ing large fires and explosions that include the following key areas:

I I

(a)

Fire fighting response strategy with the following elements:

1.

2.

3.

4.

5.

Pre-defined coordinated fire response strategy and guidance Assessment of mutual aid fire fighting assets Designated staging areas for equipment and materials Command and control I Training of response personnel The licensee shall fu,lyimplement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards continqency plans, including amendments made pursuant to provisions of the Mis~llaneous 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 conta in Safeguards Information protected under.10 CFR 73.21, is entitled: "Calvert Cliffs Nuclear Power !Plant Security Plan, Training and Qualification Plan, and Safeguards Conting~ncy Plan, Revision 1" submitted May 19, 2006.

Amendment No. 273 Revised by letter dated July 11, 2007 JtJ::>f-P.-r'\\A /~

D.

(b)

(c)

I Operations to mitigate fuel damage considering the following:

1.

Protection and use of personnel assets 2.

! Communications 3.

! Minimizing fire spread 4.

i Procedures for implementing integrated fire response I strategy

• 5.

.! Identification of readily available pre-staged equipment 6.

I Training on integrated fire response strategy 7.

I Spent fuel pool mitigation measures i

. I Acti~ns to minimize release to include consideration of:

I*i 1.

i.Water spray scrubbing 2.

! Dose to onsite responders

The licensee shall fully implement and maintain in effect all provisions of the Cornrnission-approved physical security, training and qualification, and safeguards conti nqency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Sea rch Req uirements revisions tot 0 CFR 7~.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50J54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Calvert Cliffs Nuclear Power pl ant Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 1" submitted dated May 19, 2006.

I

}useer \\\\ 8 il

)

D.

(c) 4.

.Procedures for implementing integrated fire response lstrateqy 5.

!Identification of readily available pre-staged equ ipment 6.

T raining on integrated fire response strategy 7.

[Spent fue lpool mitigation measures Actions to minimize release to include consideration of:

i 1.

!W ater spray scrubbing 2.

!Dose to onsite responders E.

The Calvert Cliffs Nuclear Power Plant, Inc., sha ll implement and maintain in effect all provisions ofithe approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SER dated September 14,1 979, and Supplements dated October 2, 1980; March 18, 1982; and September;27, 1982; and Exemptio ns dated August 16,1 982; April 21, 1983; March !1 5, 1984; August 22, 1990; and April 7, 1999 subject to the following provision: The Ca lvert Cliffs Nuclear Power Plant, Inc. may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain !safe shutdown in the event of a fire.

F.

At the time of the next scheduled update to the FSAR required pursuant to 10 CFR 50.71(e)(4) fdllowing the issuance of this renewed license, the licensee shall update the FSA~ to include the FSAR supplement submitted pursuant to 10 CFR 54.2 1(d), as amended and supplemented by the program descriptio ns in Appendix E to.the Saf.ety Evaluation Report, NUREG-1 705. Until that FSAR update is complete, the licensee may make changes to the programs described in Appendix E withoutiprior Com mission approval, provided that the licensee eva luates each such thange pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

I i

G.

Any future actions listed in Appendix E to the Safety Eva luation Report, NUREG-1705, shall be included in the FSAR. The licensee shall complete these actions by August 13, i2016.

Amendment No. 250 Revised by letter dated July 11, 2007

INSERT A (6)

Reactor Vessel In-Service Inspection Interval Extension As part of Calvert Cliffs Nuclear Power Plant's relief request to extend the reactor vessel In-Service Inspection interval (if approved), Calvert Cliffs shall submit to the NRC the information and analyses specified in paragraph (e) of the proposed 10 CFR 50.61a given in 72 FR 56275, following completion of each American Society of Mechanical Engineers (ASME) Code,Section XI, Category B-A and B-D reactor vessel weld inspection. The information and analyses shall be submitted within one year of the completion of each inspection. Once the final 10 CFR 50.61a is effective, the required information and analyses specified in paragraph (e) of the final 10 CFR 50.61a shall be the information submitted to the NRC.

lNSERT B (8)

Reactor Vessel In-Service Inspection Interval Extension As part of Calvert Cliffs Nuclear Power Plant's relief request to extend the reactor vessel In-Service Inspection interval (if approved), Calvert Cliffs shall submit to the NRC the information and analyses specified in paragraph (e) of the proposed 10 CFR 50.61a given in 72 FR 56275, following completion of each American Society of Mechanical Engineers (ASME) Code, Section Xl, Category B-A and B-D reactor vessel weld inspection. The information and analyses shall be submitted within one year of the completion of each inspection. Once the final 10 CFR 50.61a is effective, the required information and analyses specified in paragraph (e) of the final 10 CFR 50.61a shall be the information submitted to the NRC.