B13380, Proposed Tech Specs Re Semiannual Radioactive Effluent Release Rept,Monthly Operating Repts,Technical Repts Supporting Cycle Operation,Special Repts & Record Retention.Pages Omitted from 890728 Submittal
| ML20248E457 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 09/29/1989 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20248E455 | List: |
| References | |
| B13380, NUDOCS 8910050241 | |
| Download: ML20248E457 (10) | |
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Docket No. 50-213 B13380 f
Attachment 1 Haddam Neck Plant Proposed T1chnical Specification Changes (0mitted From July 28, 1989, Submittal)
October 1989 8910050241 890929 PDR ADOCK 05000213 P FDC L _ ____ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _
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ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.7 Routine Semiannual Radioactive Effluent Release Reports covering the operation of the facility during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
A supplemental report containing dose assessments for the previous year shall be submitted cnnually within 90 days aftr: January 1.
The report shall include that information delineated in the REM 0DCM.
Any changes to the REM 0DCM shall be submitted in the Semiannual Radioactive ,
Effluent Release Report. '
MONTHLY OPERATING REP 0f
- 6.9.1.8 Routine repor of operating statistics and shutdown experience shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, with one copy to the appropriate Regional Office of the NRC, and one copy to the appropriate NRC Resident Inspector, no later than the 15th of each month following the calendar month covered by the report.
TECHNICAL REPORT SUPPORTING CYCLE OPERATION 6.9.1.9 Core operating limits shall be established and documented in the TECHNICAL REPORT SUPPORTING CYCLE OPERATION before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the references provided below. The tore operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident limits) of the safety analysis are met. The TECHNICAL REPORT SUPPORTING CYCLE OPERATION, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance for each reload cycle.
References:
- 1) F. M. Akstulewicz to E. J. Mroczka, " Review of NUSCO Topical Report on Physics Methodology for PWR Reload Design (NUSCO-152)," 1.ugust 3, 1987.
- 2) A. B. Wang to E. J. Mroczka, " Safety Evaluation for Northeast Utilities Topical Report 140-1, NUSCO Thermal Hydraulic Qualification, Volume I (RETRAN)," July 26, 1988.
- 3) F. M. Akstulewicz to J. F. Opeka, "NUSCO Thermal Hydraulic Model Qualification, Volume II (VIPRE),
Topical Report "USCO 140-2," October 16, 1986.
- 4) A. B. Wang to E. J. Mroczka, " Safety Evaluation of Northeast Utilities Topical Report 151, Haddam Neck Non-LOCA Transient Analysis," October 18, 1988.
HADDAM NECK 6-15
p :. v ADMINISTRATIVE CONTROLS' L
- 5) Supplement to the Safety Evaluation by the Directorate of Licensing, U.S. Atomic Energy Commission Docket No.
50-213, Connecticut Yankee Atomic Power company,.Haddam Neck Plant, December 27, 1974.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555, with one copy to the appropriate Regional Office of the NRC, and one copy to the-appropriate NRC Resident Inspector, within the time period specified for each report.
1 6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.2 The following records shall be retained for at least 5 years:
- a. Records and logs of facility operation covering time interval at each power level;
- b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to o nuclear safety;
- c. All REPORTABLE EVENTS;
- d. Records of surveillance activities, inspections,.and calibrations required by these Technical Specifications;
- e. Records of reactor tests and experiments;
- f. Records of changes made to the procedures required by Specification 6.8.1; g, Records of radioactive shipments;
- h. Records of sealed source and fission detector leak tests and results;
- i. Records of annual physical inventory of all sealed source material of record; and 6.10.3 The following records shall be retained for the duration of the facility Operating License:
- a. Record and drawing changes reflecting facility design modifications made to systems and equipment described in the FSAR;
- b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories; HADDAM NECK 6-16
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ADMINISTRATIVE CONTROLS
- c. Records of facility radiation and contamination surveys;
- d. Records of radiation exposure for all individuals entering radiation control areas;
- e. Records of gaseous and liquid radioactive material released to the environs;
- f. Records of transient or operational cycles for those facility components identified in Table 5.7-1;
- g. Records of training and qualification for current members of the facility staff;
- h. Records of inservice inspections performed pursuant to these Technical Specifications;
- i. Records of quality assurance activities required by the Quality Assurance Manual not listed in Specification 6.10.2;
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR i Part 50.59; '
- k. Records of meetings of the PORC and the NRB;
- 1. Records for Environmental Qualification.
- m. Records of reviews performed for changes made to the Radiological Effluent Monitoring and Offsite Dose Calculation Manual (REM 0DCM) and the Process Control Program.
6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for, personnel radiation protection shall be prepared consistent with the requirement 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 paragraph 20.203(c)(5) of 10 CFR Part 20, in lieu of the " control device" or " alarm signal" required by paragraph 20.203(c), each high radiation area, as defined in 10 CFR Part 20, in which the intensity of radiation is greater than 100 mR/h but less than 1000 mR/h at 45 cm (18 in.)
from the radiation source or from any surface which 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 (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates equal to or less than 1000 mR/h, provided they are otherwise following HADDAM NECK 6-17 i
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plant radiation protection procedures for entry into such high radiation areas. 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; or
- 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 levels in the area have been established and personnel have been made knowledgeable of them; or
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Health Physics Supervisor in the RWP.
6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels greater than 1000 mR/h at 45 cm (18 in.) from the radiation source or from any surface which the radia-tion penetrates shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the shift supervisor on duty and/or heaith physics supervision. 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 and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
For individual high radiation areas accessible to personnel with radiation levels of greater than 1000 mR/h that are located within large areas, such as PWR containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device or continually guarded.
6.13 RADIOLOGICAL EFFLUENT MONITORING AND OFFSITE.JLOSE O CALCULATION MANUAL (REM 0DCM)
Section I, Radiological Effluents Monitoring Manual, shall outline the sampling and analysis programs to determine the concentration of radioactive materials released offsite as well as dose commitments to individuals in those exposure pathways and for those radionuclides released as a result of facility operation. It shall also specify operating guidelines for RADIOACTIVE WASTE TREATMENT SYSTEMS and report content.
Section II, the Offsite Dose Calculation Manual, shall describe tha methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculations of HADDAM NECK 6-18
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ADMINISTRATIVE CONTROLS gaseous and liquid effluent monitoring instrumentation Alarm / Trip Setpoints consistent with the applicable LCO's contained in these Technical Specifications.
Changes to the REMODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3.m. This documentation shall contain:
- 1) Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s), and
- 2) A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
- b. Shall become effective after review and acceptance by PORC and the approval of the Station Superintendent.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire REHM or ODCM, as appropriate, as a part of or concurrent with the Semiannual Radioactive Effluent Relean Report for the period of the report in which any change was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
6.14 RADI0 ACTIVE WASTE TREATMENT Procedures for liquid and gaseous radioactive effluent discharges from the facility shall be prepared, approved, maintained and adhered to for all operations involving offsite releases of radioactive effluents. These l- procedures shall specify the use of appropriate RADI0 ACTIVE WASTE TREATMENT I SYSTEMS utilizing the guidance provided in the REM 0DCM.
The Solid RADI0 ACTIVE WASTE TREATMENT SYSTEM shall be operated in accordance l
with the PROCESS CONTROL PROGRAM to process wet radioactive wastes to meet l
shipping and burial ground requirements.
6.15 SYSTEMS INTEGRITY The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. This program shall include the following:
- a. Provisions establishing preventive maintenance and periodic visual inspection requirements, and
- b. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.
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.j.16 PASS /Samolina and Analysis of Plant Effluents The licensee _shall. implement and maintain a program which will ensure the.
capability to obtain and analyze reactor coolant, radioactive iodines and
~ particulate in plant gaseous effluents, and containment atmosphere samples under accident conditions. :This program shall include the following:
a.- Training of personnel
- b. ' Procedures for sampling and analysis, and
- c. . Provisions _for maintenance of sampling and analysis equipment.
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3/4.4 REACTOR COOLANT SYSTEM i 1
l BASES 1
1 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation i and maintain DNBR above that point which provides 95% confidence at a 95% probability level that DNB has not occurred during all normal operations and anticipated transients. In MODES 1 and 2 with one reactor coolant loop not in operation this specification requires that the plant remain below 65%
power. With less than the required reactor coolant loops in operation, the plant shall be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The loop isolation /
valves are required to be OPERABLE in the operating loops in order to terminate the primary to secondary leak path in the event of a steam generator tube rupture.
In MODE 3, two reactor coolant loops provide sufficient heat removal capability for removing core decay heat even in the event of a bank withdrawal accident. Single failure considerations require that three loops be OPERABLE. A single reactor coolant loop provides sufficient heat removal capability for decay heat if a bank withdrawal accident can be prevented (i.e., by opening the reactor trip system breakers or de-energizing the control rod drive lift coils). Single failure considerations require that two loops be OPERABLE.
In MODE 4, two reactor coolant loops provide sufficient heat removal capability for removing decay heat even in the event of a bank withdrawal accident. Single failure considerations require that three loops be OPERABLE. A single reactor coolant or RHR loop provides sufficient heat removal capability for decay heat if a bank withdrawal accident can be prevented, i.e., by opening the reactor trip system breakers or de-energizing the control rod drive lift coils. Single failure considerations require that two loops be OPERABLE.
In MODE 5 with reactor coolant loops filled, a single RHR loop provides sufficient heat removal capability for removing decay heat. Operation of an RHR loop is not required during a reactor coolant system heatup provided reactor coolant pumps are operating in at least two unisolated loops with steam generator secondary side narrow range water level greater than 25%. A bank withdrawal accident is prevented by opening the reactor trip system breakers or de-energizing the control rod drive lift coils. Single failure <
considerations require that at least two RHR loops be OPERABLE.
In MODE 5 with reactor coolant loops not filled, a single RHR loop provides sufficient heat removal capability for removing decay heat. A bank withdrawal accident is prevented by opening the reactor trip system breakers or de-energizing the control rod drive lift coils. Single failure considerations and the unavailability of the steam generators as a heat removing component require that at least two RHR loops be OPERABLE.
The operation of one Reactor Coolant Pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with baron reduction will, therefore, be within the capability of operator recognition and control.
HADDAM NECK B3/4 4-1