ML022460339

Proposed Amendment 184a to Technical Specifications Corrections

ML022460339
Person / Time
Site:	Kewaunee
Issue date:	08/20/2002
From:	Coutu T Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-02-075
Download: ML022460339 (15)

Text

Kewaunee Nuclear Power Plant N490 Highway 42 Kewaunee, WI 54216-9511 920 388 2560 Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, Wl 54241 920 755.2321 Kewaunee / Point Beach Nuclear Operated by Nuclear Management Company, LLC NRC-02-075 August 20, 2002 10 CFR 50.90 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Ladies/Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Proposed Amendment 184a to the Kewaunee Nuclear Power Plant Technical Specifications Corrections

Reference:

Letter from Mark E. Warner (NMC) to Document Control Desk (NRC), "Proposed Amendment 184 to the Kewaunee Nuclear Power Plant Technical Specifications,"

dated June 7, 2002 In the referenced letter, several strikeout pages were inadvertently omitted and one page, TS 2.3-2, contained an error. During the processing of this proposed amendment several TS pages had formatting changes which were included in the affected pages attachment but were excluded from the strikeout pages attachment. Additionally, an error occurred in the submittal process which cause a factor, f(AI), to be submitted as F2(AI). contains those pages omitted while attachment 2 contains the corrected page, both strikeout and affected copies.

We apologize for any inconvenience this may have caused.

To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respects these statements are not based entirely on my personal knowledge, but on information furnished by cognizant NMC employees and consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

NMC Ee Committed to Nuclear Excellence

Docket 50-305 NRC-02-075 August 20, 2002 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on August 20, 2002.

S' erely Thomas Coutu Site Vice President Kewaunee Nuclear Power Plant GOR Attach.

cc -

US NRC, Region III US NRC Senior Resident Inspector Electric Division, PSCW Letter from T. Coutu (NMC)

To Document Control Desk (NRC)

Dated August 20, 2002 Proposed Amendment 184a Omitted Strikeout Pages Table TS 1.0-1 TS 6.2-1 TS 6.7-1 TS 6.8-1 TS 6.9-1 TS 6.9-2 TS 6.9-3 TS 6.19-1 TS 6.20-1

TABLE TS 1.0-1 FREQUENCY NOTATIONS PAGE 1 OF I Proposed Amendment 184 06/10/2002 NOTATION FREQUENCY Shift (S)

At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Daily (D)

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Weekly (W)

At least once per 7 days Monthly (M)

At least once per 31 days Quarterly (Q)

At least once per 92 days Semiannual (SA)

At least once per 184 days Refueling (R)

At least once per 18 months Reactor Startup (S/U)

Prior to each reactor startup N.A.

Not aApplicable

6.2 ORGANIZATION

a. Off-Site Staff The off-site organization for plant management and technical support shall be as described in the Operational Quality Assurance Program Description.

b. Facility Staff The plant organization shall be as described in the Operational Quality Assurance Program Description.

1. Each on-duty shift complement shall consist of at least:

A. One Shift Manager (SRO)

B. Two licensed Reactor Operators C. Two Nuclear Auxiliary Operators D. Deleted E. One Radiation Technologist

2. While above COLD SHUTDOWN, the on-duty shift complement shall consist of the personnel required by TS 6.2.b.1 and an additional SRO.

3. In the event that one of the shift members becomes incapacitated due to illness or injury or the Radiation Technologist has to accompany an injured person to the hospital, reactor operations may continue with the reduced complement until a replacement arrives. In all but severe weather conditions, a replacement is required within two hours.

4. At least one licensed operator shall be in the control room when fuel is in the reactor.

5. Two licensed operators, one of which shall be an SRO, shall be present in the control room when the unit is in an operational MODE other than COLD SHUTDOWN or REFUELING.

6. REFUELING OPERATIONS shall be directed by a licensed SRO assigned to the REFUELING OPERATION who h2s no other concurrent responsibilities during the REFUELING OPERATION.

7. When the reactor is above the COLD SHUTDOWN condition, a qualified Shift Technical Advisor shall be within 10 minutes of the control room.

c. Organizational Changes Changes not affecting safety may be made to the off-site and facility staff organizations.

Such changes that are described in the Technical Specifications shall be reported to the Commission in the form of an application for license amendment within 60 days of the implementation of the change.

Proposed Amendment 184 TS 6.2-1 06/10/2002

6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a SAFETY LIMIT is violated:

a.

The reactor shall be shut down and operation shall not be resumed until authorized by the Commission.

b.

The Report shall be prepared in accordance with 10 CFR 50.72 and 10 CFR 50.73.

Proposed Amendment 184 TS 6.7-1 06/10/2002

6.8 PROCEDURES

a. Written procedures and administrative policies shall be established, implemented and maintained that meet the requirements and recommendations of Section 5.2.2, 5.2.5, 5.2.15 and 5.3 of ANSI N18.7-1976.

b. Changes to procedures are made in accordance with the provisions of ANSI N18.7-1976 Section 5.2.2, except that-temporary changes which clearly do not change the intent of the procedure shall, as a minimum, be approved by two individuals knowledgeable in the area affected one of which holds an active SRO license at Kewaunee.

c. Procedures are reviewed in accordance with the provisions of ANSI N18.7-1976, Section 5.2.15, h-weve-.

The biennial review requirement is accomplished through alternate programs as dci~bed in the OQAPD.

Proposed Amendment 184 TS 6.8-1 06/10/2002

6.9 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted.

a. Routine Reports

1. Startup Report A summary report of plant startup and power escalation testing shall be submitted following: (1) receipt of an OPERATING license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant. The report shall address each of the tests identified in the USAR and shall in general include a description of the measured values of the OPERATING conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.

Any corrective actions that were required to obtain satisfactory operation shall also be described.

Any additional specific details required in license conditions based on other commitments shall be included in this report.

Startup reports shall be submitted within: (1) 90 days following completion of the startup test program, (2) 90 days folloUving resumption or commencement of commercial power operation, or (3)g9nine months following initial criticality, whichever is earliest.

If the Startup RK--p-rt does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

2. Annual Reporting Requirements Routine OPERATING reports covering the operation of the unit during the previous calendar year shall be submitted prior to March 1 of each year. Items reported in this category include:

A. Deleted Proposed Amendment 184 TS 6.9-1 06/10/2002

B. As per applicable, portions of Regulatory Guide 1.16, a tabulation on an annual basis of the nimber of station, utility, and other personnel (including contractors) receiving exposures > 100 mrerm/yr and their associated person rem exposure according to work and job functionsO) e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and REFUELING.

The dose assignment to various duty functions may be estimates based on pocket dosimeter er-.(TLD). Small exposures totaling < 20% of the individual total dose need not 5e a~counted for. In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.

C. Challenges to and failures of the pressurizer power operated relief valves and safety valves.(2)

D. This report shall document the results of specific activity analysis in which the reactor coolant exceeded the limits of TS 3.1.c.l.A during the past year. The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceededl.

(2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radioiodine concentrations-.

(3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded-.

(4) Graph of the 1-131 concentration and one other radioiodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level;--ad.

(5) The time duration when the specific activity of the reactor coolant exceeded the radioiodine limit.

(1) This tabulation supplements the requirements of Section 20.2206(b) of 10 CFR Part 20.

(2) Letter from E. R. Mathews (WPSC) to D. G. Eisenhut (U.S. NRC) dated January 5, 1981.

Proposed Amendment 184 TS 6.9-2 06/10/2002

3. Monthly OPERATING Report Routine reports of OPERATING statistics and shutdown experience shall be submitted on a monthly basis to the Document Control Desk, U.S. Nuclear Regulatory Commission, Washington, D.C., 20555, with a copy to the appropriate Regional Office, to be submitted by the fifteenth of each month following the calendar month covered by the report.

b. Unique Reporting Requirements

1. Annual Radiological Environmental Monitoring Report A. Routine Radiological Environmental Monitoring Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the OFF-SITE DOSE CALCULATION MANUAL (ODCM) and Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

2. Radioactive Effluent Release Report Routine Radioactive Effluent Release Reports covering the operation of the unit for the previous calendar year shall be submitted by May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the PCP, and in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

3. Special Reports A. Special reports may be required covering inspections, test and maintenance activities. These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.

(1) Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix D, 10 CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555 within the time period specified for each report.

Proposed Amendment 184 TS 6.9-3 06/10/2002

6.19 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS(1')

Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid):

a. Shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the PORC. The discussion of each change shall contain:

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59.

2. Sufficient information to support the reason for the change without benefit of additional or supplemental information-.

3. A description of the equipment, components and processes involved and the interfaces with other plant systems-,

4. An evaluation of the change-; whie*h-that shows the predicted releases of radioactive materials in liquid and gaseous -effuents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;_.

5. An evaluation of the change; whieh-that shows the expected maximum exposures to individuals in the UNRESTRICTED-AREA and to the general population that differ from those previously estimated in the license applicatlon and amendments thereto-.

6. A comparison of the predicted releases of radioactive materials7 in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;_.

7. An estimate of the exposure to p!ant OPERATING personnel as a result of the change; -aý.

8. Documentation of the fact that the change was reviewed and found acceptable by the PORC.

b. Shall become effective upon review and acceptance by the PORC.

(1) Licensees may choose to submit the information called for in this TS as part of the periodic USAR update.

Proposed Amendment 184 TS 6.19-1 06/10/2002

6.20 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. The program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995. The provisions of TS 4.0.b do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program. The provisions of TS 4.0.c are applicable to the Containment Leakage Rate Testing Program.

The peak calculated containment internal pressure for the design basis loss-of-coolant accident is less than the containment internal test pressure, P,. The maximum allowable leakage rate (La) is 0.5 weight percent of the contained air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at the peak test pressure (P,) of 46 psig.

For penetrations which extend into the Aauxiliary 8building Sspecial ventilation Zzone the combined leak rate from these penetrations shall not exceed 0.10La. For penetrations which are exterior to both the Sshield R3building and the Aauxiliary 8ýbuilding Sspecial VMventilation Zzone, the combined leak rate from these penetrations shall not exceed 0.01 La.

If leak rates are exceeded, repairs and retest shall be performed to demonstrate reduction of the combined leak rate to these values.

Leakage rate acceptance criteria:

a. The containment leakage rate acceptance criterion is _< 1.0La.

b. Prior to unit startup following testing ii accordance with this program, the leakage rate acceptance criteria are < 0.6La foi Type B and C tests and < 0.75L, for the Type A test.

c. The P-personnel and E-emergency Aair L-ock leakage rates, when combined with the cumulative Type B and C leakage, shall be < 0.6La. For each air lock door seal, the leakage rate shall be < 0.005L, when tested to > 10 psig.

Proposed Amendment 184 TS 6.20-1 06/10/2002 Letter from T. Coutu (NMC)

To Document Control Desk (NRC)

Dated August 20, 2002 Proposed Amendment 184a Corrected Page TS 2.3-2 (Strikeout)

TS 2.3-2 (Affected)

3.

Reactor Coolant Temperature A.

Overtemperature AT <ATo [Ki-K2(T-T')I+-rS+K3(P-P')-f(A,)]

1 + T2 S where

=

Indicated AT at RATED POWER, OF

=

Average temperature, OF

=

567.30F

=

Pressurizer pressure, psig

=

2235 psig

=

1.11

=

0.0090 AT0 T

"1' P

P1 K1 K2 K3

'Tl T2 f(Ai)

=

0.000566

=

30 sec.

=

4 sec.

=

An even function of the indicated difference between top and bottom detectors of the power-_range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and q, + qb is total core power in percent of RATED POWER, such that:

(a-)1.

For qt - qb within -12, +9%, f (All) = 0.

-b-2.

For each percent that the magnitude of qt - qb exceeds +9% the

-AT tripsetpoint shall be automatically reduced by an equivalent of 2.5%

of RATED POWER.

(9)3.

For each percent that the magnitude of q, - qb exceed -12% the AT "Trip i'etpoint shall be automatically reduced by an equivalent of 1.5% of RATED POWER.

Proposed Amendment 184 TS 2.3-2 06/10/2002

3.

Reactor Coolant Temperature A.

Overtemperature AT <ATo [Kj-K 2 (T-T')I+vrS+K 3 (P-P')-f(AI)]

1 + r2 S where ATo

=

Indicated AT at RATED POWER, OF T

=

Average temperature, OF T'

=

567.30F P

=

Pressurizer pressure, psig P'

=

2235 psig K1

=

1.11 K2

=

0.0090 K3

=

0.000566 T=

30 sec.

T2

=

4 sec.

f(AI)

=

An even function of the indicated difference between top and bottom detectors of the power range nuclear ion chambers. Selected gains are based on measured instrument response during plant startup tests, where q, and qb are the percent power in the top and bottom halves of the core respectively, and q, + qb is total core power in percent of RATED POWER, such that:

1. For qt - qb within -12, +9%, f (AI) = 0.

2. For each percent that the magnitude of qt - qb exceeds +9% the AT trip setpoint shall be automatically reduced by an equivalent of 2.5% of RATED POWER.

3. For each percent that the magnitude of qt - qb exceed -12% the AT trip setpoint shall be automatically reduced by an equivalent of 1.5% of RATED POWER.

TS 2.3-2