ML20056E044
| ML20056E044 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 07/29/1993 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20056E045 | List: |
| References | |
| NUDOCS 9308190254 | |
| Download: ML20056E044 (12) | |
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' UNITED STATES j { ).1[- j -
-NUCLEAR REGULATORY COMMISSION i
g WASHINGTON, D.C. 20556-0001 l
ENTERGY OPERATIONS. INC.
QQQET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE t
Amendment No. 84' License No.-NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found.that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated May 7, 1993, complies with the standards and i
requirements of the Atomic Energy Act of 1954, as amended-(the Act),
l and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the i
provisions of the Act, and the rules and regulations of the
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Commission; y
C.
There is reasonable assurance (i) that the activities authorized by
-i this amendment can be conducted without' endangering the health and safety of the'public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; j
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety'of the public;. and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable. requirements'have been satisfied.
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9308190254 930729
_PDR ADDCK 05000382 i
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 84, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in iccordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q
Harry Ro Acting Director Project Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 29, 1993
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ATTACHMENT TO LICENSE AMENDMENT NO. 84 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 I
Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES XVII XVII 1-4 1-4 3/4 11-8 3/4 11-8 6-19 6-19 t
6-24 6-24 t
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1 1
INDEX 1
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ADMINISTRATIVE CONTROLS l,
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SECTION EAGE 6.5.2 SAFETY REVIEW COMMITTEE...................................
6-10 i
FUNCTION...............................................
6-10 i
COMPOSITION............................................
6-10 ALTERNATES............................................. 10
.j CONSULTANTS............................................
6-10 MEETING FREQUENCY......................................
6-11
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QU0 RUM.................................................
6-11 REVIEW.................................................
6-11 AUDITS.................................................
6-12 AUTH0RITY..............................................
6-13 REC 0RDS................................................
6-13 6.6 REPORTABLE EVENT ACTI0N.....................................
6-13 6.7 SAFETY LIMIT VIOLATION......................................
6-13 6.8 PROCEDURES AND PR0 GRAMS.....................................
6-14 6.9 REPORTING RE0VIREMENTS......................................
6-16 6.9.1 ROUTINE REP 0RTS...........................................
6-16 STARTUP REP 0RT.........................................
6-17 ANNUAL REP 0RTS.........................................
6-17 --
MONTHLY OPERATING REP 0RT...............................
6-18 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT.....
6-18 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT.............
6-19 l
INDUSTRIAL SURVEY OF T0XIC CHEMICALS REPORT............
6-20 6.9.2 SPECIAL REP 0RTS...........................................
6-20 6.10 ' RECORD RETENTION...........................................
6-20 WATERFORD UNIT 3 XVII Amendment No. 68,84
j INDEX-
-ADMINISTRATIVE CONTROLS
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SECTION PAGE-l
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6.11 RADIATION PROTECTION PR0 GRAM...............................
6-22 6.12 HIGH RADIATION AREA........................................
6-22 6.13 PROCESS CONTROL PR0 GRAM....................................
6-23
-t 6.14 0FFSITE DOSE CALCULATION MANUAL............................-
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WATERFORD - UNIT 3 XVIII Amendment No. 68
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i DEFINITIONS CORZ ALTERATION 1.9 CORE ALTERATION shall be the movement or manipulation of any component within the reactor pressure vessel with the vessel head removed and fuel in the vessel.
Suspension of CORE ALTERATION shall not preclude completion of movement of a component to a safe conservative position.
DOSE EQUIVALENT I-131 j
t 1.10 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/
gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133. I-134, and I-135 actually present.
l The thyroid dose conversion factors used for this calculation shall be those listed in Table III of' TID-14844, " Calculation of Distance Factors for Power and Test Reactor Sites."
i E - AVERAGE DISINTEGRATION ENERGY
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1.11 I shall be the average (weighted in proportion to the concentration of I
each radionuclide in the reactor coolant at the time _of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at
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least 95% of the total noniodine activity in the coolant.
h ENGINEERED SAFETY FEATURES RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURES RESPONSE TIME shall be that time interval
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from when the monitored parameter exceeds its ESF actuation setpoint at the.
channel sensor until the ESF equipment is capable of performing its' safety 1
function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).
Times shall include diesel generator starting and sequence loading delays where applicable.
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FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
IDENTIFIED LEAKAGE 1.14 IDENTIFIED LEAKAGE shall be:
y Leakage (except CONTROLLED LEAKAGE) into closed systems, such as 1
a.
pump seal or valve. packing leaks that are captured, and conducted to a sump or collecting tank, or WATERFORD - UNIT 3 1-3
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V
-DEFINITIONS IDENTIFIED LEAKAGE (Continued) b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
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c.
Reactor Coolant System leakage through a steam generator to the i
secondary system.
MEMBER (S) 0F THE PUBLIC 1.15 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupa-tionally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to' service equipment or make deliveries. This category does include persons who use portions of the site for recreational, 3
occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.16 The OFFSITE DOSE CALCULATION MANUAL (0DCM) 'shall contain the methodology and parameters used in the calculation of offsite doses resulting from radio-active gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmen-tal Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls' and Radiological Environmental Monitoring Programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and '
Annual Radioactive Effluent Release Reports required by Specification 6.9.1.7 l
and 6.9.1.8.
OPERABLE - OPERABILITY 1.17 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attendant instrumentation, controls, electrical power, cooling or-seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
OPERATIONAL MODE - MODE 1.18 An OPERATIONAL MODE (i.e. MODE) shall correspond to' any one inclusive combination of core reactivity condition, power. level and average reactor r
coolant temperature specified in Table 1.2.
WATERFORD UNIT 3 1-4 Amendment No. 68, 84 4
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Pages 3/4 11-1 through 11-7 have been deleted.
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.WATERFORD - UNIT-3 3/4 11 AMENDMENT NO. 17, 68
' l Next page is 3/4.11-8
4 RADIOACTIVE EFFLUENTS LIOUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following,pnprotected outdoor tanks'shall be limited to less than or equal to 1.57 x 10 curies,* excluding tritium and dissolved or entrained noble gases.
For outside temporary storage tanks, the curie content shall be limited such that a rupture will not. result in exceeding 10 CFR Part 20 limits at the UNRESTRICTED AREA boundary.
a.
PWST b.
Outside temporary tank APPLICABILITY: At all times.
ACTION:
a.
With the quantity of radioactive material in any of the above listed tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within the limit, and describe.the events leading to l
this condition in the next Annual Radioactive Effluent Release-
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Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
f SURVEILLANCE REOUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the' above listed tanks shall be determined to be within the above limit by ' analyzing a representative sample o'f the tank's contents at least once per 7 days when radioactive materials are being added to the tank.
- Based on 80% tank capacity and an MPC of 2 x 10~5 pC1/mL Cesium-137 equivalent,10 CFR Part 20, Appendix B. Table II.
I WATERFORD - UNIT 3 3/4 11-8 Amendment No. 84
ADMINISTRATIVE CONTROLS l
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
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f 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation I
of the unit during the previous 12 months of operation shall be submitted within 60 days after January 1 of each year. The report shall include a i
summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent l
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 1 to 10 CFR Part 50.
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WATERFORD - UNIT 3 6-19 Amendment No. 68, 84
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,a-ADMINISTRATIVE CONTROLS
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INDUSTRIAL SURVEY OF T0XIC OR HAZARDOUS CHEMICALS REPORT
- 6. 9.1. 9 Surveys and' analyses of major industries in the vicinity of Waterford 3 which could have significant inventories ~of. toxic chemicals onsite to determine impact on safety shall be perfonned and submitted to the Commission at least once every 4 years.
6.9.1.10 A survey of major pipelines (> 4. inches) within a 2-mile radius of
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Waterford 3, which contain explosive or flammable materials and may represent a hazard to Waterford 3, including scaled engineering drawings or maps which indicate the pipeline locations, shall be performed and submitted to the Commission at least once every 4 years.
SPECIAL REPORTS l
6.9.2 Special reports shall be submitted to the Regional Administrator.of the
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Regional Office of the NRC within the time period specified for each report.
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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.
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. ATERFORD - UNIT 3 6-20.
AMENDMENT NO. 68 i
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ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued) 2.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCH:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p. This document 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 10 CFR 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 the PORC and the approval of the Plant Manager.
c.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the l
report in which any change to the ODCM 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.
WATERFORD - UNIT 3 6-24 AMENDMENT NO. 68,84