ML17329A646

Proposed TS 3/4.9.7 Re Control of Loads Moving Over Spent Fuel Pool During Spent Fuel Reracking Project,Per NUREG-0612

ML17329A646
Person / Time
Site:	Cook
Issue date:	10/26/1992
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17329A645	List: ML17329A644 ML17329A646
References
RTR-NUREG-0612, RTR-NUREG-612 AEP:NRC-1146D, NUDOCS 9210300116
Download: ML17329A646 (14)

Text

ATTACHMENT 1 TO AEP'NRC'1146D EXISTING TECHNICAL SPECIFICATIONS PAGES MARKED TO REFLECT PROPOSED CHANGES 92i0300iib 921026 PDR ADOCK 05000315 P PDR vP'LC

'ocket No.315 Page 4 of 6 Amendment No, 31 2.C(4)The license may Proceed with and is required to complet h modifications identified in Table 1 of the Fire Protection Safety Evaluation Report, for the Donald C.Cook Nuclear Plant dated June 4, 1979.These modifications shall be completed in accozdance with the dates contained in Table 1 of that SER ox Supplements thereto.Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.

Amendment No.118,136 (5)S ent Fuel Pool Stora e The licensee is authori d to store D.C.Cook, Unit 1 and Unit 2 fuel assemblies new or irradiated in any combination up to a total of fuel assemblies in the shared spent fuel pool at the Donald C.Cook Nuclear Plant sub)ect to the following conditions:

~1 Fuel stoned in the spent fuel pool shall not have ap'oNWaA enrichment greater than 4.95X Uranium-235.

'1 Amend<.ent No.122*2.D (6)Deleted by Amendment 80.Physical Protection The licensee shall fully implement and maintain in effect all pz'ovisions of the Commission-approved physical security;guard 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 50'4(p).The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald C.Cook Nuclear Plant Security Plan," wi:h revisions submitted thxough July 21, 1988;"Donald C.Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 18, 1986;and"Donald C.Cook Nucleaz'lant Safeguards Contingency Plan," with revisions submitted thz'ough June 10, 1988.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.H (7)The provisions of Specification 3/4.9.7 are not applicable for loads being moved over the pool for the duration of the spent.fuel pool reracking project.Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612~"Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged..

4' Docket No.316 Page 6 of 11 Amendment No.104,121 (q)Deleted by Amendmenr 2.(r)Deleted by Amendment 68 (s)S ent Fuel Pool Stora e The licensee is authorized to s re D.C.Cook, Unit 1 and Unit 2 fuel assemblies, ne or irradiated in any combination, up to a total of fuel assemblies in the shared spent fuel pool*t the Donald C.Cook Nuclear Plant subject to the following conditions:

floYYil Fuel stored in the spent fuel pool shall not have ap'nrichment greater than 4.95X Uranium-235.

• Amendment 3 deleted Paragraph (s), Amendment 13 added a new Paragraph (s).(t)Deleted by Amendment 63.2.C.(7)'Secondary Mater Chemistry Monitorin Pro ram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.

This program shall be described in the s"ation chemistry manual and shall include: 1.Identification of a sampling schedule for the critical parameters and control points for these parameters; 3.Identification of the procedures used to measure the values of the critical parameters; Identification of process sampling points;Amendment No.1S 4.Procedure for the recording and management of data;5.Procedures defining corrective actions for off control point chemistry conditions; and 6.A procedure identifying (a)the authori"y responsible for the interpretation of the data, and (b)the sequence and timing of administrative events required to initiate corrective actions.

Docket No.316 Page 7 of 11 D.Physical Protection Amendment No.109 The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard 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 plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald C.Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988;"Donald C.Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 19, 1986;and"Donald C.Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.E.Deleted by Amendment 63.F.Deleted by Amendment 6.Q.Amendment No.34 S stem Inte ri The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.This program shall include the following:

1.Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.Integrated leak test requir'ements for each system at a frequency not to exceed refueling cycle intervals.

(u)The provisions of Specification 3/4.9.7 are not applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project.Control of loads moving over the spent fuel pool during the spent fuel pool reracking pro]ect shall comply with the criteria of NUREG-.0612>"Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks required by T/S 3/4.9.7, disengaged.

ATTACHMENT 2 TO AEP:NRC:1146D PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

'ocket No.315 Page 4 of 6 Amendment No~31 2.C(4)The licensee may proceed with and is required to complete the modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C.Cook Nuclear Plant dated June 4, 1979.These modifications shall be completed in accordance with the dates contained in Table 1 of that SER or Supplements thereto.Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.

(5)S ent Fuel Pool Stora e Amendment No.118,136 The licensee is authorized to store D.C.Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated in any combination up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.Cook Nuclear Plant subject to the following conditions:

Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95%Uranium-235.

(6)Deleted by Amendment 80.(7)The provisions of Specification 3/4.9.7 are not applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project.Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612"Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged.

• 2.D Ph sical Protection Amendment No.122 The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard 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 plans, which contain Safeguards information protected under 10 CFR 73.21, are entitled: "Donald C.Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988;"Donald C.Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 18, 1986;and"Donald C.Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.

Docket No.316 Page 6 of ll (q)Deleted by Amendment 2.(r)Deleted by Amendment 68.(s)S ent Fuel Pool Stora e Amendment No.104, 121 The licensee is authorized to store D.C.Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated in any combination, up to a total of 3613 fuel assemblies in the shared spent fuel pool at the Donald C.Cook Nuclear Plant subject to the following conditions:

Fuel stored in the spent fuel pool shall not have a nominal enrichment greater than 4.95%Uranium-235.

+Amendment 3 deleted Paragraph (s), Amendment 13 added a new Paragraph (s).(t)Deleted by Amendment 63.(u)The provisions of Specification 3/4.9.7 are not applicable for loads being moved over the pool for the duration of the spent fuel pool reracking project.Control of loads moving over the spent fuel pool during the spent fuel pool reracking project shall comply with the criteria of NUREG-0612,"Controls of Heavy Loads at Nuclear Power Plants." Administrative controls shall be in place to prevent any load not rigged in compliance with the criteria of NUREG-0612 from passing over the spent fuel pool with the crane interlocks, required by T/S 3/4.9.7, disengaged.

2.C.(7)Secondar Water Chemistr Monitorin Pro ram The licensee shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation.

This program shall be described in the station chemistry manual and shall include: 1.Identification of a sampling schedule for the critical parameters and control points for these parameters; 2.Identification of the procedures used to measure the values of the critical parameters; 3.Identification of process sampling points;Amendment No.18 4.Procedure for the recording and management of data; Docket No~316 Page 7 of 11 5.Procedures defining corrective actions for off control point chemistry conditions; and 6.A procedure identifying (a)the authority responsible for the interpretation of the data, and (b)the sequence and timing of administrative events required to initiate corrective actions.D.Physical Protection Amendment No.109 The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard 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 plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Donald C.Cook Nuclear Plant Security Plan," with revisions submitted through July 21, 1988;"Donald C.Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 19, 1986;and"Donald C.Cook Nuclear Plant Safeguards Contingency Plan," with revisions submitted through June 10, 1988.Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.E.Deleted by Amendment 63.F.Deleted by Amendment 6.**Q.Amendment No.34 S stem Inte rit The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.This program shall include the following:

1.Provisions establishing preventive maintenance and periodic visual inspection requirements, and 2.Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.