ML042120203

Tech Spec Pages for Amendment 228 Various Administrative and Editorial Changes

ML042120203
Person / Time
Site:	Fort Calhoun
Issue date:	07/23/2004
From:	NRC/NRR/DLPM/LPD4
To:
Wang A,/NRR/DLPM/415-1445
Shared Package
ML042120345	List: ML042110411 ML042120203
References
TAC MC1535
Download: ML042120203 (9)

Text

TECHNICAL SPECIFICATIONS TABLE 3-3 (Continued)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF MISCELLANEOUS INSTRUMENTATION AND CONTROLS Surveillance Channel Descriptlon Function Frequency Surveillance Method

14. Not Used I

15. Reactor Coolant System a. Check a. Calculation of reactor coolant flow rate.

Flow

16. Pressurizer Pressure a. Check S a. CHANNEL CHECK

17. Reactor Coolant Inlet a. Check S a. CHANNEL CHECK Temperature

18. Low-Temperature Set- a. Test PM a. CHANNEL FUNCTIONAL TEST (excluding point Power-Operated actuation)

Relief Valves

b. Calibrate R b. CHANNEL CALIBRATION (1" Required to be performed within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> after k95.00% reactor thermal power following power escalation.

3.1 - Page 17 Amendment No. 8239O6G4 S31-.=, 228

TECHNICAL SPECIFICATIONS TABLE 3-5 (continued)

MINIMUM FREQUENCIES FOR EQUIPMENT TESTS USAR Section Test FrequencV Reference 10a. (continued) 2. Laboratory Testing*"

Verify, within 31 days after removal, On a refueling frequency or every 720 that a laboratory test of a sample of hours of system operation or after any the charcoal adsorber, when obtained structural maintenance on the HEPA filter or In accordance with Regulatory charcoal adsorber housing or following Position C.6.b of Regulatory Guide significant painting, fire or chemical release in 1.52, Revision 2. March 1978, shows a ventilation zone communicating with the methyllodlde penetration less than system.

0.175% when tested in accordance with ASTM D3803-1989 at a temperature of 30nC (861F) and a relative humidity of 70%.

3. Overall System Oneration

a. Each circuit shall be operated. Ten hours every month.

b. The pressure drop across the R combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 9 Inches of water at system design flow rate.

c. Fan shall be shown to operate R within +/- 10% design fow.

4. Automatic and manual Initiation of R the system shall be demonstrated.

'*Tests shall be performed In accordance with applicable section(s) or ANSI N510-1980.

3.2 - Page 7 Amendment No. 4-124,4281698-4-98, 228

TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)

(iii) Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported prior to resumption of plant operation. The written followup of this report shall provide a description of Investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

3.17 -Page 7 Amendment No. 4i~j 228

TECHNICAL SPECIFICATIONS 3.0 SURVEILLANCE REQUIREMENTS 3.17 Steam Generator Tubes (Continued)

Basis The surveillance requirements for inspection of the steam generator tubes and tube sleeves ensure that the structural Integrity of this portion of the RCS will be maintained. The program for in-service inspection of the steam generator tubes is based on a modification of Regulatory Guide 1.83, Revision 1, dated July 1975. The program for in-service inspection of steam generator tube sleeves is based on a modification of EPRI PWR Steam Generator Examination Guidelines, Revision 5, Dated September 1997. In-service inspection of steam generator tubing and tube sleeves is essential in order to maintain surveillance of the conditions of the tubes and sleeves In the event that there Is evidence of mechanical damage or progressive degradation due to design, manufacturing errors, or in-service conditions that lead to corrosion.

In-service inspection of steam generator tubing and tube sleeves also provides a means of characterizing the nature and cause of any tube or sleeve degradation so that corrective measures can be taken.

Tubes with defects may be repaired by a Combustion Engineering, Inc. Leak Tight Sleeve. The technical bases for sleeving repair are described in the Proprietary Combustion Engineering, Inc. Report CEN-630-P, Revision 02, "Repair of 3/4" O.D.

Steam Generator Tubes Using Leak Tight Sleeves," June 1997.

Whenever the results of any steam generator tubing in-service inspection fall into Category C-3, these results will be promptly reported to the Commission prior to the resumption of plant operation. Such cases will be considered by the Commission on a case-by-case basis and may result in a requirement for analysis, laboratory examinations, tests, additional eddy-current inspection, and revision of the Technical Specifications, if necessary.

3.17 -Page IO Amendment No. 404, 195j228

TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.4 Training 5.4.1 A retraining and replacement training program for the plant staff shall be maintained under the direction of the Manager - Training and shall meet or exceed the requirements of Section 6 of ANSI/ANS 3.1-1993, as modified by Regulatory Guide 1.8, Revision 3, dated May 2000 and 10 CFR Part 55.

5.5 Not Used I

5.6 Not Used I 5.0 - Page 4 Amendment No. 9,19,38,841,09,01

-115,410,32,133,140,157,160, 168,160,181, 202, 228

TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.7 Safety Limit Violation 5.7.1 The following action shall be taken in the event a Safety Limit is violated:

I

a. The unit shall be placed in at least HOT SHUTDOWN within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

I 5.8 Procedures 5.8.1 Written procedures and administrative policies shall be established, implemented and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Fire Protection Program Implementation; and

d. All programs specified in Specification 5.11 through 5.21.

5.8.2Temporary changes to procedures of 5.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant supervisory staff, at least one of whom holds a Senior Reactor Operators License.

5.0 - Page 5 Amendment No. 8,19,38,84,,

1185,14,157,160,151,202,216, 228

TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.8 Procedures (Continued)

c. The change is documented, reviewed by a qualified reviewer and approved by either the plant manager or the department head designated by Administrative Controls Standing Orders as the responsible department head for that procedure within 14 days of Implementation.

5.8.3 Written procedures shall be implemented which govern the selection of fuel assemblies to be placed in Region 2 of the spent fuel racks (Technical Specification 2.8). These procedures shall require an independent verification of initial enrichment requirements and fuel burnup calculations for a fuel bundle to assure the "acceptance" criteria for placement in Region 2 are met. This Independent verification shall be performed by Individuals or groups other than those who performed the initial acceptance criteria assessment, but who may be from the same organization.

5.9 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 appropriate NRC Regional Office unless otherwise noted.

5.9.1 Routine Reports

a. Not Used 5.0 - Page 6 Amendment No. 9,14 ,35,75,1 49,16 0,169,2O2 228

TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements (Continued)

b. Annual Occupational Exposure Report. An annual occupational exposure report shall be submitted on or before April 30 of each year.

The report shall consist of a tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mremlyr and their associated man rem exposure according to work and job functions,3 e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance), waste processing, and refueling outages. The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted 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. Monthly Operating Report. Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S.

Nuclear Regulatory Commission, Document Control Desk, with a copy to the appropriate Regional Office, no later than the fifteenth of each month following the calendar month covered by the report.

5.9.2 Not Used 5.9.3 Special Reports Special reports shall be submitted to the appropriate NRC Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification where appropriate:

a. In-service inspection report, reference 3.3.

b. Tendon surveillance, reference 5.21.

c. Containment structural tests, reference 3.5.

d. DELETED

e. DELETED

f. DELETED

g. Materials radiation surveillance specimens reports, reference 3.3.

h. DELETED

i. Post-accident monitoring Instrumentation, reference 2.21

j. Electrical systems, reference 2.7(2).

SI This tabulation supplements the requirements of § 20.2206 of 10 CFR Part 20.

5.0 - Page 7 Amendment No. b,24.3 110,113,114. 133,117,106 ,216,24,228

TECHNICAL SPECIFICATIONS 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements (Continued) 5.9.4 Unique Reporting Requirements

a. Annual Radioactive Effluent Release Report The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year of operation shall be submitted before 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

1) consistent with the objectives outlined in the ODCM and PCP, and

2) in conformance with 10 CFR 50.36a. and Section IV.B.1 of Appendix Ito 10 CFR 50.

b. Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May I 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 objectives outlined In (1) the ODCM and (2)Section IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR 50.

c. Not Used 5.9.5 Core Operating Limits Renort

a. Core Operating Limits shall be established and documented in the Core Operating Limits Report (COLR) before each reload cycle or any remaining part of a reload cycle.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC as follows:

1. OPPD-NA-8301-P-A, "Reload Core Analysis Methodology Overview" approved version as specified Inthe COLR.

2. OPPD-NA-8302-P-A, "Neutronics Design Methods and Verification", approved version as specified in the COLR.

5.0- Page 8 Amendment No. 0,241,35,38,16,75,86, 99,110,113,414,133,141,144,117, 152,157,160,164,178,185,196, 202,228