ML031970452

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Supplement to License Amendment Request for Removal of Obsolete And/Or Expired License Conditions from the Unit 1 and Unit 2 Operating Licenses, Editorial Changes to the Unit 1 and Unit 2 Operating Licenses, and Administrative Changes....
ML031970452
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 07/02/2003
From: Joseph E Pollock
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP:NRC:3090
Download: ML031970452 (39)
v • d • e


Text

Indiana Michigan Power Company 500 Circle Drive Buchanan, Ml 49107 1395 INDIANA MICHIGAN POWER July 2, 2003 AEP:NRC:3090 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001

SUBJECT:

Donald C. Cook Nuclear Plant, Unit 1 and Unit 2 Docket Nos. 50-315 and 50-316 Supplement to License Amendment Request For Removal of Obsolete and/or Expired License Conditions from the Unit 1 and Unit 2 Operating Licenses, Editorial Changes to the Unit 1 and Unit 2 Operating Licenses, and Administrative Changes to the Unit 1 and Unit 2 Technical Specifications

REFERENCE:

Letter from J. E. Pollock, Indiana Michigan Power Company to Nuclear Regulatory Commission Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos.

50-315 and 50-316 License Amendment Request for Removal of Obsolete and/or Expired License Conditions from the Unit I and 2 Operating Licenses (OLs), Editorial Changes to the Unit 1 and Unit 2 OLs, and Administrative Changes to the Unit 1 and Unit 2 Technical Specifications," AEP:NRC:2090, dated August 23, 2002.

Dear Sir or Madam:

This letter provides a supplement to a previously proposed license amendment involving administrative and editorial changes to the Donald C. Cook Nuclear Plant (CNP) Unit 1 and Unit 2 Operating Licenses (OLs) and Technical Specifications (TSs).

In the referenced letter, Indiana Michigan Power Company (I&M) proposed to remove obsolete and/or expired license conditions from the Unit I and Unit 2

- 0(1

U. S. Nuclear Regulatory Commission AEP:NRC:3090 Page 2 OLs, make editorial changes to the Unit 1 and Unit 2 OLs, and make administrative changes to the Unit 1 and Unit 2 TSs. Subsequent to submittal of the referenced letter, I&M identified additional obsolete and/or expired license conditions that should be deleted and additional administrative changes that should be made to the TSs. I&M also identified the need for additional changes to previously submitted pages. Accordingly, I&M is proposing to include these additional changes in the amendment proposed by the referenced letter.

Additionally, in the referenced letter, I&M proposed to add a new reference "e" to TS 6.9.1.9.2. The description of this new reference inaccurately stated that the new reference reflects the upgrade to VANTAGE+ fuel for "Cycle 17." The description should have stated that the new reference reflects the upgrade to VANTAGE+ fuel for "future Unit 2 cycles." to this letter provides an affirmation regarding the statements made and matters set forth in this letter. Enclosure 2 provides a detailed description and safety analysis to support the additional proposed changes. Attachments IA and lB provide TS pages marked to show proposed changes for Unit 1 and Unit 2, respectively. Attachments 2A and 2B provide TS pages with the proposed changes incorporated for Unit 1 and Unit 2, respectively. Attachments 3A and 3B provide the OL pages marked to show the proposed changes for Unit 1 and Unit 2, respectively. Attachments 4A and 4B provide the OL pages with the proposed changes incorporated for Unit 1 and Unit 2, respectively.

The additional changes proposed in this letter are consistent with those proposed in the referenced letter, in that they do not affect plant operation or design.

Therefore, the information in this letter does not alter the validity of the original evaluation of no significant hazards considerations performed in accordance with 10 CFR 50.92 documented in Enclosure 2 to the referenced letter. The environmental assessment provided in Enclosure 2 to the referenced letter also remains valid. Therefore, no additional no significant hazard considerations or environmental assessment is provided in Enclosure 2 to this letter.

No pending amendment requests affect the TS pages that are submitted in this request. If any future submittals affect these TS pages, I&M will coordinate the changes to the pages with the Nuclear Regulatory Commission Project Manager to ensure proper TS page control when the associated license amendment requests are approved.

U. S. Nuclear Regulatory Commission AEP:NRC:3090 Page 3 There are no new regulatory commitments made in this letter. If you have any questions or require additional information, please contact Mr. Brian A. McIntyre, Manager of Regulatory Affairs, at (269) 697-5806.

Sincerely, J. E. Pollock Site Vice President DB/rdw

Enclosures:

1 Affirmation 2 Supplement to License Amendment Request For Removal of Obsolete and/or Expired License Conditions From the Unit 1 and Unit 2 Operating Licenses, Editorial Changes to the Unit 1 and Unit 2 Operating Licenses, and Administrative Changes to the Unit 1 and Unit 2 Technical Specifications Attachments:

IA and lB TS Pages Marked to Show Proposed Changes 2A and 2B Proposed TS Pages 3A and 3B OL Pages Marked to Show Proposed Changes 4A and 4B Proposed OL Pages c: K. D. Curry, Ft. Wayne AEP, w/o enclosures/attachments J. E. Dyer, NRC Region III J. T. King, MPSC, w/o enclosures/attachments MDEQ - DW & RPD, w/o enclosures/attachments NRC Resident Inspector J. F. Stang, Jr., NRC Washington, DC

Enclosure 1 to AEP:NRC:3090 AFFIRMATION I, J. E. Pollock, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.

Indiana Michigan Power Company J. E. Pollock Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME y ComiDAY OF , 2003 JUUE E.NEWMIULLER Notry Public, Berrlen County, Ml MY Comm ission EWires Aum 22,2004 U Notari Public My Commission Expires j-;-%

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- -' - N to AEP:NRC:3090 -PageI Supplement to License Amendment Request For Removal of Obsolete and/or Expired License Conditions from the Unit 1 and Unit 2 Operating Licenses. Editorial Changes to the Unit 1 and Unit 2 Operating Licenses, and Administrative Changes to the Unit 1 and Unit 2 Technical Specifications

1.0 DESCRIPTION

In Reference 1, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Unit 1 and Unit 2, proposed to remove obsolete and/or expired license conditions from the Unit 1 and Unit 2 Facility Operating Licenses (OLs), make editorial changes to the Unit 1 and Unit 2 OLs, and make administrative changes to the Unit 1 and Unit 2 Technical Specifications (TSs). Subsequent to submittal of Reference 1, I&M identified additional obsolete and/or expired license conditions that should be deleted and additional administrative changes that should be made to the TSs. I&M also identified the need for additional changes to previously submitted pages. Accordingly, I&M is proposing to include these additional changes in the amendment proposed by Reference 1.

2.0 PROPOSED CHANGE

I&M proposes administrative changes to the following Unit 1 and Unit 2 TSs:

Unit 1 Unit 2 TS 6.9.1.9.2.e Page 6-12 TS 3.4.8, Action a Page 3/4 4-20 TS 6.12.l.c Page 6-14 TS 4.7.5.l.d Page 3/4 7-16 TS 5.6.2.a Page 5-9 TS 6.12.1.c Page 6-14 These changes are shown on Attachments IA, 1B, 2A, and 2B. Unit 1 Page 6-12, and Unit 2 Pages 3/4 7-16, and 5-9, are in addition to those submitted by Reference 1. Unit 1 Page 6-14, and Unit 2 Pages 3/4 4-20, and 6-14 replace the corresponding pages submitted by Reference 1.

In addition, I&M proposes to delete the following obsolete and/or expired license conditions from the Unit 1 and Unit 2 OLs:

Unit 1 Unit 2 License Condition 2.C(5) License Condition 2(3)(s)

License Condition 2.C(l 1) License Condition 2(3)y These changes are shown on Attachments 3A, 3B, 4A, and 4B. These license pages replace the corresponding pages submitted by Reference 1.

to AEP:NRC:3090 Page 2

3.0 BACKGROUND

Since the original issuance of the Unit 1 and Unit 2 OLs, I&M has incorporated several additional requirements (i.e., license conditions) into the license via the 10 CFR 50.90 license amendment process. In some cases, subsequent license amendments have removed certain license conditions that were no longer applicable. In other cases, license conditions have become obsolete or have expired, but remain part of the OLs. In Reference 1, I&M proposed to remove those license conditions that no longer apply.

In Reference 1, I&M also proposed several administrative changes to the Unit 1 and Unit 2 TS to correct administrative errors which were introduced by prior license amendments.

This supplement proposes deletion of two additional license conditions that are now obsolete, and proposes correction of additional administrative errors which were not included in Reference 1. These changes are being proposed so that the OL will retain only those license conditions that remain pertinent to current plant operations, and so that the TSs are administratively accurate.

4.0 TECHNICAL ANALYSIS

I&M proposes the following administrative changes to specific Unit 1 and Unit 2 TSs.

Proposed TS Changes Unit 1 I&M proposes to add a new reference "e" to TS 6.9.1.9.2. The new reference "e" consists of "WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report"." The new reference "e" reflects the upgrade to VANTAGE+ fuel for future Unit I cycles. This upgrade to the VANTAGE+ fuel was approved in License Amendment Nos. 148 and 134, dated August 27, 1990 (Reference 2).

I&M proposes to revise a plant position title in TS Section 6.12.1.c requirements for controlling high radiation areas. I&M proposes to replace "facility Health Physicist" with "Plant Radiation Protection Manager." The proposed change reflects CNP's current organizational structure.

Unit 2 In Reference 1, I&M proposed to correct a typographical error in Unit 2 TS 3.4.8, Limiting Condition for Operation (LCO), Action "a." Currently, Action "a" reads "...for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval for exceeding the limit..." However, Action "a" should read "...for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit..." to be consistent with the Unit I TS. When this page was issued in Reference 1, the to AEP:NRC:3090 Page 3 change was not made correctly, in that the wrong "for" was changed to "or." I&M has provided a corrected page in this supplement.

I&M proposes to add a new line of text to Unit 2 TS 3/4.7.5, "Control Room Ventilation System." The new line of text consists of "4.7.5.l.d After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by either:" This line of text was inadvertently left off during reconciliation of several TS change documents associated with Amendment 240 (Reference 3).

I&M proposes to add the word "Westinghouse" to the beginning of 5.6.2.a. This word was proposed in Reference 4; however, in License Amendment 220, dated January 6, 2000 (Reference 5), this word was not included in the Unit 2 TS.

I&M proposes to revise a plant position title in TS Section 6.12.1.c requirements for controlling high radiation areas. I&M proposes to replace "facility Health Physicist" with "Plant Radiation Protection Manager." The proposed change reflects CNP's current organizational structure.

Obsolete and/or Expired License Conditions I&M also proposes to delete the following obsolete and/or expired license conditions from the Unit 1 and Unit 2 OLs.

Unit 1

  • License Condition 2.C(5) - "Spent Fuel Pool Storage - The licensee is authorized to store D. C. Cook Unit 1 and Unit 2 fuel assemblies, new or irradiated 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 nominal enrichment greater than 4.95% Uranium-235."

This license condition is being deleted because it contains redundant information. The information contained in this condition is also found in Section 5.6, Fuel Storage, of the TSs. Specifically, Section 5.6.1.1.c contains design criteria for fuel assemblies that are to be stored in Region 1, Region 2 and Region 3. This design criterion for fuel assemblies is based upon their assembly average burnup versus initial nominal enrichment. Section 5.6.4 states, "The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies."

  • License Condition 2.C(l1) - "During the essential service water pump replacement, a one-time extension of the Technical Specification 3.4.7.1 Action a and b requirement that an inoperable essential service water loop be restored to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be extended to 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />. This extension is applicable only during the to AEP:NRC:3090 Page 4 preplanned replacement of an essential service water pump with a modified pump and may not be used when as essential service water pump is found to be inoperable. The extension is subject to the following conditions:"
  • "This allowance may be invoked once for each essential service water pump to allow replacement of the pump with a modified pump.
  • This allowance is applicable until January 31, 2003.
  • When the essential service water loops are declared inoperable during the pump replacement, the systems supported by the essential service water system need not enter their limiting conditions for operation action statements."

This license condition was a one-time extension which was added to the license by Amendment 270, dated September 9, 2002 (Reference 6). This license condition provided a one-time 140-hour allowed outage time for the essential service water (ESW) system, to allow ESW pump replacement. The ESW pump replacement project has been completed; therefore, this license condition is no longer applicable and can be deleted.

Unit 2 License Condition 2(3)(s) - "Spent Fuel Pool Storage - The licensee is authorized to store D. C. Cook, Unit 1 and Unit 2 fuel assemblies, new or irradiated 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."

This license condition is being deleted because it contains redundant information. The information contained in this condition is also found in Section 5.6, Fuel Storage, of the TSs. Specifically, Section 5.6.1.1.c contains design criteria for fuel assemblies that are to be stored in Region 1, Region 2 and Region 3. This design criterion for fuel assemblies is based upon their assembly average burnup versus initial nominal enrichment. Section 5.6.4 states, "The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies."

to AEP:NRC:3090 Page 5

  • License Condition 2.(3)y - "During the essential service water pump replacement, a one-time extension of the Technical Specification 3.7.4.1 Action a and b requirement that an inoperable essential service water loop be restored to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be extended to 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />. This extension is applicable only during the preplanned replacement of an essential service water pump with a modified pump and may not be used when an essential service water pump is found to be inoperable. The extension is subject to the following conditions:"
  • "This allowance may be invoked once for each essential service water pump to allow replacement of the pump with a modified pump.
  • This allowance is applicable until January 31, 2003.
  • When the essential service water loops are declared inoperable during the pump replacement, the systems supported by the essential service water system need not enter their limiting conditions for operation action statements."

This license condition was a one-time extension which was added to the license by Amendment 251, dated September 9, 2002 (Reference 6). This license condition provided a one-time 140-hour allowed outage time for the ESW system, to allow ESW pump replacement. The ESW pump replacement project has been completed; therefore, this license condition is no longer applicable and can be deleted.

5.0 REFERENCES

1. Letter from J. E. Pollock, I&M to U. S. Nuclear Regulatory Commission (NRC)

Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Docket Nos.

50-315 and 50-316 License Amendment Request for Removal of Obsolete and/or Expired License Conditions from the Unit 1 and 2 Operating License (OLs), Editorial Changes to the Unit 1 and Unit 2 OLs, and Administrative Changes to the Unit 1 and Unit 2 Technical Specifications," AEP:NRC:2090, dated August 23, 2002

2. Letter from Timothy G. Colburn, NRC, to Milton P. Alexich, I&M, "Amendment Nos.

148 and 134 to Facility Operating License Nos. DPR-58 and DPR-74: (TAC Nos.

75395, 75396, and 76816)," dated August 27, 1990

3. Letter from John F. Stang, NRC, to Robert P. Powers, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 - Issuance of Amendments (TAC Nos. MA9394 and MA9395),"

dated October 24, 2001 to AEP:NRC:3090 Page 6

4. Letter from R. P. Power, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Technical Specification Change Request Fuel Rod Zirlo Cladding and Integral Fuel Burnable Absorber (IFBA) Requirements," Cl 199-13, dated November 3, 1999
5. Letter from John F. Stang, NRC, to Robert P. Powers, I&M, "Issuance of Amendments

- Donald C. Cook Nuclear Plant, Units 1 and 2, Re: Fuel Rod Zirlo Cladding and Integral Fuel Burnable Absorber Requirements (TAC Nos. MA7041 and MA7042),"

dated January 6, 2000

6. Letter from John F. Stang, NRC, to A. Christopher Bakken III, I&M, "Donald C. Cook Nuclear Plant, Units 1 and 2 - Issuance of Amendments (TAC Nos. MB5729 and MB5730)," dated September 9,2002

Attachment IA to AEP:NRC:3090 TECHNICAL SPECIFICATION PAGES MARKED TO SHOW PROPOSED CHANGES REVISED PAGES UNIT 1 6-12 6-14

6.0 ADMINISTRATIVE CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.

Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a. Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4,
b. Rod Drop Time Limits for Specification 3/4.1.3.3,
c. Shutdown Rod Insertion Limits for Specification 3/4.1.3.4,
d. Control Rod Insertion Limits for Specification 3/4.1.3.5,
e. Axial Flux Difference for Specification 3/4.2.1, f Heat Flux Hot Channel Factor for Specification 3/4.2.2,
g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and
h. Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

a. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary),
b. WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary),
c. WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),
d. WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).

L261OAP;M7V T TO1 Coe COOK NUCLEAR PLANT-UNIT I Page 6-12 AMENDMENT 69, 14, 474, 489, 206,226 I

6.0 ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to 10 CFR20.1601(c), in lieu of the requirements of 10 CFR 20.1601(a) and (b), each high radiation area in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mrem but less than or equal to 1000 mrem in I hour at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicista MIEcii=if M Ein the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the radiation level at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates is greater than 1000 mrem in I hour. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift S on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor i Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas. In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT I Page 6-14 AMENDMENT 94, i, 454,4 89, 2N, 245

Attachment lB to AEP:NRC:3090 TECHNICAL SPECIFICATION PAGES MARKED TO SHOW PROPOSED CHANGES REVISED PAGES UNIT 2 3/4 4-20 3/4 7-16 5-9 6-14

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to I microCurie per gram DOSE EQUIVALENT 1-131, and
b. Less than or equal to 100/ E microCuries per gram of gross radioactivity.

APPLICABILITY: MODES 1, 2, 3,4 and 5 ACTION:

MODES 1, 2 and 3

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval for E exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with T,, less than 5000 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the specific activity of the reactor coolant greater than 100/ EmicroCuries per gram, be in HOT STANDBY with T., less than 5001F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1,2, 3,4 and 5

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT 1-131 or greater than 100/ E microCuries per gram, perform the sampling and analysis requirements of itemn 4a of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.

I SURVEILLANCE REOUIREMENTS 4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the I

sampling and analysis program of Table 4.4-4.

With T., greater than or equal to 5000 F.

I COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-20 AMENDMENT 129

3/4 314.7 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

I LMAe- vi 7( iiiiobro Ii Drt~l bither53

1. Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister shows a penetration of less than or equal to 1.0% for radioactive methyl iodide when the sample is tested in accordance with ASTM D3803-1989, 300 C, 95% R.H.; or I
2. Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples shows a penetration of less than or equal to 1.0% for radioactive methyl iodide when the samples are tested in accordance with ASTM D3803-1989, 300 C, 95% R.H. and the samples are prepared by either: I a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b) Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also:

a) Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfin +/- 10%, and b) Verifying that the HEPA filter banks remove 2 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfin +/- 10%.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-16 AMENDMENT 240, I

5.0 DESIGN FEATURES 5.6 FUEL STORAGE (Continued)

CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with:

a. ad Fuel assemblies having either a maximum enrichment of 4.55 weight % U-235, or an enrichment between 4.55 and 4.95 weight % U-235 with the minimum number of integral fuel burnable absorber pins as shown on Figure 5.6-4 (interpolation of the Boron-10 loading between 1.OX and 1.5X and between 1.5X and 2.OX is acceptable);
b. k~ff S 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR;
c. kff
  • 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; and
d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

DRAINAGE I

5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'4".

CAPACITY 5.6A The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

COOK NUCLEAR PLANT-UNIT 2 Page 5-9 AMENDMENT U, "3, 4, 4B,486,

-8, 220

6.0 ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of 10 CFR 20.1601(a) and (b), each high radiation area in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mrem but less than or equal to 1000 mrem in I hour at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist fl tion aria in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the radiation level at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates is greater than 1000 mrem in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift a on duty and/or the Plant Health Physicis t (ElantRadiation Protection S oper aria eF . Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas. In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT 2 Page 6-14 AMENDMENT 80, 4-6, 48, 4U, 20, 226

Attachment 2A to AEP:NRC:3090 PROPOSED TECHNICAL SPECIFICATION PAGES REVISED PAGES UNIT 1 6-12 6-14

6.0 ADMINISTRATIVE CONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.

Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.

CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:

a. Moderator Temperature Coefficient Limnits for Specification 3/4.1.1.4,
b. Rod Drop Time Limits for Specification 3/4.1.3.3,
c. Shutdown Rod Insertion Limits for Specification 314.1.3.4,
d. Control Rod Insertion Limits for Specification 3/4.1.3.5,
e. Axial Flux Difference for Specification 3/4.2.1,
f. Heat Flux Hot Channel Factor for Specification 3/4.2.2,
g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and
h. Allowable Power Level for Specification 3/4.2.6.

6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:

a. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary),
b. WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary),
c. WCAP-10216-P-A, Revision )A, "Relaxation of Constant Axial Offset Control/FQ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),
d. WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
e. WCAP-12610-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," July 1991 (Westinghouse Proprietary).

COOK NUCLEAR PLANT-UNIT I Page 6-12 AMENDMENT 69, 4, 4-4, 489, 20 2m,

6.0 ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of 10 CFR 20.1601(a) and (b), each high radiation area in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mrem but less than or equal to 1000 mrem in I hour at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit'. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Plant Radiation Protection Manager in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the radiation level at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates is greater than 1000 mrem in I hour. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Manager on duty and/or Plant Radiation Protection Manager. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas. In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT I Page 6-14 AMENDMENT 94, 4, 4-4, 489, 26, 4,

Attachment 2B to AEP:NRC:3090 PROPOSED TECHNICAL SPECIFICATION PAGES REVISED PAGES UNIT 2 3/4 4-20 3/4 7-16 5-9 6-14

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:

a. Less than or equal to I microCurie per gram DOSE EQUIVALENT 1-131, and
b. Less than or equal to 100/ E microCuries per gram of gross radioactivity.

APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1,2 and 3

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with T., less than 5000 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. I
b. With the specific activity of the reactor coolant greater than 100/ E microCuries per grain, be in HOT STANDBY with Ta.g less than 5000 F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1,2, 3,4 and 5

a. With the specific activity of the reactor coolant greater than I microCurie per gram DOSE EQUIVALENT 1-131 or greater than 100/ E microCuries per gram, perform the sampling and analysis requirements of item 4a of Table 4.4-4 until the specific activity of the reactor coolant is restored to within its limits.

SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the reactor coolant shall be determined to be within the limits by performance of the sampling and analysis program of Table 4.4-4.

With T., greater than or equal to 5000F.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-20 AMENDMENT429,

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.7 PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

d. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by either:
1. Verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister shows a penetration of less than or equal to 1.0% for radioactive methyl iodide when the sample is tested in accordance with ASTM D3803-1989, 300C, 95% R.H.; or
2. Verifying within 31 days after removal that a laboratory analysis of at least two carbon samples shows a penetration of less than or equal to 1.0% for radioactive methyl iodide when the samples are tested in accordance with ASTM D3803-1989, 30 0C, 95% R.H. and the samples are prepared by either:

a) Emptying one entire bed from a removed adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed, or b) Emptying a longitudinal sample from an adsorber tray, mixing the adsorbent thoroughly, and obtaining samples at least two inches in diameter and with a length equal to the thickness of the bed.

Subsequent to reinstalling the adsorber tray used for obtaining the carbon sample, the system shall be demonstrated OPERABLE by also:

a) Verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm +/- 10%, and b) Verifying that the HEPA filter banks remove 2 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 6000 cfm +/- 10%.

COOK NUCLEAR PLANT-UNIT 2 Page 3/4 7-16 AMENDMENT 24,

5.0 DESIGN FEATURES 5.6 FUEL STORAGE (Continued)

CRITICALITY - NEW FUEL 5.6.2 The new fuel storage racks are designed and shall be maintained with:

a. Westinghouse fuel assemblies having either a maximum enrichment of 4.55 weight % U-235, or I

an enrichment between 4.55 and 4.95 weight % U-235 with the minimum number of integral fuel burnable absorber pins as shown on Figure 5.6-4 (interpolation of the Boron-10 loading between 1.OX and 1.5X and between 1.SX and 2.OX is acceptable);

b. kff
  • 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR;
c. k~ff
  • 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.7 of the UFSAR; and
d. A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.

DRAINAGE 5.6.3 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 629'4".

CAPACITY 5.6.4 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 3613 fuel assemblies.

COOK NUCLEAR PLANT-UNIT 2 Page 5-9 AMENDMENT A4, 4143, 447, 4, 86, 198,A,

6.0 ADMINISTRATIVE CONTROLS 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA 6.12.1 Pursuant to 10 CFR 20.1601(c), in lieu of the requirements of 10 CFR 20.1601(a) and (b), each high radiation area in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mrem but less than or equal to 1000 mrem in I hour at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit'. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Plant Radiation Protection Manager in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the radiation level at 30 cm from the radiation source or 30 cm from any surface that the radiation penetrates is greater than 1000 mrem in I hour. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Manager on duty and/or the Plant Radiation Protection Manager. Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas. In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.

Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

COOK NUCLEAR PLANT-UNIT 2 Page 6-14 AMENDMENT 80, 4-36, I38, 6-5,240,226,

Attachment 3A to AEP:NRC:3090 FACILITY OPERATING LICENSE PAGES MARKED TO SHOW PROPOSED CHANGES REVISED PAGES UNIT 1 Page 3 of 6 Page 4 of 6

Docket No. 315 Page 3 of 6 (3) Less than Four Loop Operation The licensee shall not operate the reactor at power levels above P-7 (defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less that E5B four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.

Amendment No. 2.C(4) Indiana Michigan Power Company shall implement and maintain, in effect, all 31,194,208 provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 1985, June 30, 1986, January 28, 1987, May 26, 1987, June 16, 1988, June 17, 1988, June 7, 1989, February 1, 1990, February 9, 1990, March 26, 1990, April 26, 1990, March 31, 1993, April 8, 1993, December 14, 1994, January 24, 1995, April 19, 1995, June 8, 1995, and March 11, 1996, subject to the following provision:

The licensee 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.

(5) Spent Fuel Pool Storamq Amendment No. The licensee is authorized to store D. C. Cook Unit I and Unit 2 fuel assemblies, 118,136,169 new or irradiated 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 nominal ennrnment greater than 1.85% Uranium-235 (6) Deleted by Amendment 80.

(7)

A, Secondarv Water Chemistrv Monitorina Proaram 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; Amendment No.

36 2. Identification of the procedures used to measure the values of the critical parameters;

3. Identification of process sampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemistry conditions; and

Docket No. 315 Page 4 of 6

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.

Amendment No. (8) The povisions of Specification 31.9.7 are not applicable for loads being moved 169 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 Control of Heavy Loads at Nuclear Power Plants.' Administrative controls shall be in place to prevent any load not igged in compliance with the criteria of NUREG 0612 from passing over the spent fuel pool with the crane intcrlocks, required by T4S 3/.9.7, disengaged.

Amendment No. 2.C(G) The steam generator tube inspection surveillance requirements of Technical 227 Specification 1.1.5.3 have been extended until the start of cycle 17, not to exceed January 31, 2001. In the event the steam generators are replaced prior to the start of cycle 17, the retired steam generators are exempted frmA further surve'illance under T!S 1.4.5.3.

Amendment No. 2.C(10) Technical Specification surveillance requirements 1.6.5.3.1.b.3. 1.6.5.3.1.b.4, and 265 4.6.5.3.1.b.5 need not be performed until prior to ascension into Mode 4 at the crmpletion of fuel cycle 18 refueling outage. if Unit I enters Made 5 for sufficient duration prior to the fuel cycle 18 refueling outage, l&M will perform the surreilance testing required by TS C.6.5.3.1..3, 1-.6.5.341.4t, and 4.6.C.341.b.5.

Amendment No. 2.G(11) During the essential service water pump replacement, a one -time-extens6ion of the 270 Technical Specification 3.1.7.1 Action a and b requirement that an inoperable essential servie water loop be Festored to an operable status within 7-2 hours may be extended to 110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br />. This extension is applicable only during the preplanned replacement of an essential service water pump Vith a modified pump and may not be used when an essential service water pump is found to be inoperable. The extension is subject to the following conditions:

  • This allowane may be invoked ocre far each essential sermvice water pump to allow replacement of the pump faith a modified pump.

_ This allowance may be invoked once for each Unit 4 essential service water loop when the assdciated Unit 2 essential servi e water pump is being repla-edr.

This will be done in acor4dance vYith Unit 2 Technical Specification 3.7.1.4

- This allowance isapplicable until January 31, 2003.

a tArnn a aenal eni^nd unt.rArcane nrn Aa,-nrmA4 innnar"hoa Hl rinn AHo nags I ----

_ wulllv

--- _r replacement, the systems supported by the essential servk l-wa ter systei; .+4r-Hui _tor their r At efittlF liritir_ ouril ifirdwi- Niffiltaiu

- - -C o

&t:rr r +i^ eie eot For ye f6wiUm(dfib 04di Upt.-Iddidil dUtifJ11 WdOdliftilLb.

  • 2.D Physical Protection Amendment No. The licensee shall fully implement and maintain in effect all provisions of the 122 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

Attachment 3B to AEP:NRC:3090 FACILITY OPERATING LICENSE PAGES MARKED TO SHOW PROPOSED CHANGES REVISED PAGES UNIT 2 Page 5 of 10 Page 6 of 10 Page 7 of 10

Docket No. 316 Page 5 of 10 Amendment (0) Indiana Michigan Power Company shall implement and maintain, No. 12,180, 192 in 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 SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22,1983, December23, 1983, March 16,1984, August 27, 1985, June 30, 1986, January 28, 1987, May 26, 1987, June 16, 1988, June 17, 1988, June 7, 1989, February 1, 1990, February 9, 1990, March 26,1990, April 26, 1990, March 31, 1993, April 8, 1993, December 14, 1994, January 24, 1995, April 19, 1995, June 8, 1995, and March 11, 1996, subject to the following provision:

The licensee 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.

Amendment (p) Deleted by Amendment No. 64,121 (q) Deleted by Amendment 2.

(r) Deleted by Amendment 68.

(S) Spent F eal P

Amendment The lirensce is authorized to store D. G. Ceok, Unit 1 and Unit 2 No. 104, 121, 15 fuel assemblie, nE or irradiated up to a total of 3613 fuel assemblies ir then shred pent fuel pool at the Donald C. Cook Nuclear Plant subject to the falowina oenditions:

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 Paradraph ( n 63 (t) Deleted by Amendment 63.

Amendment (u) The provisions of Spccification 311.9.7 are not applicable for No. 15 loads being moved over the pool for the duration of the spent fuel pool reracking project. Control of loads moving over the epent fuel pool during the spent fuel pool reracking project shall oemply with the criteria of NUREG AControls 0612, of Heavy ILads at Nuclear Power Plants." Adminibtrtative ontrols shall be in plaer to prevent any load not rigged in cormplianre with the criteria of NUREG 0612 from passing over the spent fuil poel with the crane mintelerks, Feured by TCS 314.9.7, disengaged.

v. Secondary Water Chemistry Monitoring Program 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:

Docket No. 316 Page 6 of 10

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 4. Procedure for the recording and management of No. 18 data;
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.

Amendment w. The steam generator tube inspection sureIlane No. 232 maximruminpecction interal of Technical Spci~fation 4.4.5.3 is extended until the star of cycle 13, but no latcw than june 30, 20Ws Amendment x. The emergency diesel generator engine Technical Nel 234 Specification surveillane requirements of 1.8.1.1.2.c.1 and 41.8.1.4.2.e.7 have been extended to allow their performance during refueling outage 13, but no later than December 31, 2001.

The station batter; rervice testing Technicral Specification surveillance requirements 4.8.2.3.2.d and 1.8.2.5.2.d have been extended to allow them to be performed during the refueling outage 13, but no later than December 31, 2001.

Amendmegt y. During the essential ser'evice water pump replacement, a one time tension of the Techniral Sperification 3.7.1.1 Action a and b equirement that an inoperable essential seovice watei loop be restered to an operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be extended to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />. This extensionis appliable only during the preplanned replarement of an essential sewrice water pump with a modified pump and may not be used when an essential rer.ire water pump is found to be inoperable. The extensieo is subiet to the followin oundi~tionn:

  • This allowance may be inv once for each essential servioc water pump to allow replacement of the pump with a modified pump.

Docket No. 316 Page 7 of 10

  • s allowance is applicable until ianuar, 31. 2003.

. When the essential sear.'c water loops arc dGlarled inopreFabl during the pumpreplacement, the systems supported by the essential service water system need not rat - C -

UHief WU& 10FH2t1H[j UrJHW1WWf1b M UjJUfdk0V!1 dUtEfdri btdMifildrith.

D. Physical Protection 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 Amendment 10 CFR 73.21, are entitled: ODonald C. Cook Nuclear Plant Security No. 109 Plank with revisions submitted through July 21, 1988; *Donald C. Cook Nuclear Plant Training and Qualification Plan," with revisions submitted through December 19, 1986; and KDonald 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.

G. System Integrity Amendment The licensee shall implement a program to reduce leakage from systems No. 34 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.

H. Iodine Monitorino Amendment The licensee shall implement a program which will ensure the No. 34 capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1. Training of personnel,
2. Procedures for monitoring, and
3. Provisions for maintenance of sampling and analysis equipment.

Amendment I. In all places of this license, the reference to the Indiana and No. 29 Michigan Power Company is deleted and all references to 'the licensees" is amended to read "the licensee". The intent is to recognize the Indiana

Attachment 4A to AEP:NRC:3090 PROPOSED FACILITY OPERATING LICENSE PAGES REVISED PAGES UNIT 1 Page 3 of 5 Page 4 of 5

Docket No. 315 Page 3 of 5 (3) Less than Four Loon Oeration The licensee shall not operate the reactor at power levels above P-7 (defined in Table 3.3-1 of Specification 3.3.1.1 of Appendix A to this license) with less than I four reactor coolant loops in operation until (a) safety analyses for less than four loop operation have been submitted, and (b) approval for less than four loop operation at power levels above P-7 has been granted by the Commission by amendment of this license.

Amendment No. 2.C(4) Indiana Michigan Power Company shall implement and maintain, in effect, all 31, 194, 208 provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility and as approved in the SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22, 1983, December 23, 1983, March 16, 1984, August 27, 1985, June 30, 1986, January 28, 1987, May 26, 1987, June 16, 1988, June 17, 1988, June 7, 1989, February 1, 1990, February 9, 1990, March 26, 1990, April 26, 1990, March 31, 1993, April 8, 1993, December 14, 1994, January 24, 1995, April 19, 1995, June 8, 1995, and March 11, 1996, subject to the following provision:

The licensee 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.

(5) Deleted by Amendment I (6) Deleted by Amendment 80.

(7) Secondary Water Chemistry Monitoring 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; Amendment No.

36 2. Identification of the procedures used to measure the values of the critical parameters;

3. Identification of process sampling points;
4. Procedure for the recording and management of data;
5. Procedures defining corrective actions for off control point chemistry conditions; and

Docket No. 315 Page 4 of 5

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.

(8) Deleted by Amendment 2.C(9) Deleted by Amendment 2.C(10) Deleted by Amendment 2.C(11) Deleted by Amendment

  • 2.D Physical Protection Amendment No. The licensee shall fully implement and maintain in effect all provisions of the 122 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: fDonald 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 80.

2.F. Deleted by Amendment 80.

  • 2.G In all places of this license, the reference to the Indiana and Michigan Power Amendment No. Company is deleted and all references to "the licensees' is amended to read "the 33 licensee". The intent is to recognize the Indiana and Michigan Electric Company as the sole licensee of the Donald C. Cook Nuclear Plant
  • 2.H System Integrity Amendment No.

49 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 a practical levels. The 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.

Attachment 4B to AEP:NRC:3090 PROPOSED FACILITY OPERATING LICENSE PAGES REVISED PAGES UNIT 2 Page 5 of 9 Page 6 of 9

Docket No. 316 Page 5 of 9 Amendment (a) Indiana Michigan Power Company shall implement and maintain, No. 12, 180, 192 in 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 SERs dated December 12, 1977, July 31, 1979, January 30, 1981, February 7, 1983, November 22, 1983, December23, 1983, March 16, 1984, August27, 1985, June 30, 1986, January 28, 1987, May 26, 1987, June 16, 1988, June 17, 1988, June 7, 1989, February 1, 1990, February 9, 1990, March 26, 1990, April 26, 1990, March 31, 1993, April 8, 1993, December 14, 1994, January 24, 1995, April 19, 1995, June 8, 1995, and March 11, 1996, subject to the following provision:

The licensee 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.

Amendment (p) Deleted by Amendment No. 64, 121 (q) Deleted by Amendment 2.

(r) Deleted by Amendment 68.

(S) Deleted by Amendment I

(t) Deleted by Amendment 63.

(u) Deleted by Amendment I

v. Secondary Water Chemistry Monitoring Proaram 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 4. Procedure for the recording and management of No. 18 data;
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.

Docket No. 316 Page 6 of 9

w. Deleted by Amendment
x. Deleted by Amendment
y. Deleted by Amendment D. Physical Protection 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 Amendment 10 CFR 73.21, are entitled: *Donald C. Cook Nuclear Plant Security No. 109 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 ODonald 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.

G. System Integrity Amendment The licensee shall implement a program to reduce leakage from systems No. 34 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.

H. Iodine Monitorina Amendment The licensee shall implement a program which will ensure the No. 34 capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1. Training of personnel,
2. Procedures for monitoring, and
3. Provisions for maintenance of sampling and analysis equipment.
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