ML20036B276
| ML20036B276 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/07/1993 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20036B274 | List: |
| References | |
| NUDOCS 9305180436 | |
| Download: ML20036B276 (8) | |
Text
--
i r
t h
4 i
NPF-38-138 ATTACHMENT A l
?
t f
9305180436 930507 PDR ADOCK 05000382 E
p PDR
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 i
operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or Reactor Coolant System leakage through a steam generator to the c.
t secondary system.
MEMBER (S) 0F THE PUBLIC 1.15 MEMBER (5) 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, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.16 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology P
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 Radio-active 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 Semiannual Radioactive Effluent Release Reports required by Specification 6.9.1.7 and 6.9.1.8.
OPERABLE - OPERABILITY 1
1.17 A system, subsystem, train, component, or device shall be OPERABLE or i
have OPERABILITY when it is capable of performing its specified function (s),
and when all necessary attent. ant 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).
a 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 coolant temperature specified in Table 1.2.
t WATERFORD - UNIT 3 1-4 Amendment No. 68
I t
I RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following unprotected outdoor tanks shall be limited to less than or equal to 1.57 x 10 2 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 i
this condition in the next Semiannual Radioactive Effluent Release 3
Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 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 of the tank's contents at least once per 7 days when raoioactive materials are being added to the tank.
- Based on 80% tank capacity and an MPC of 2 x 10 5 pCi/mL Cesium-137 E
equivalent, 10 CFR Part 20, Appendix B, Table II.
WATERFORD - UNIT 3 3/4 11-8
4 ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 The Semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be i
submitted within 60 days after January 1 and July 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous i
1 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 I to 10 CFR Part i
50.
l I
4 i
i l
1 I
i 1
i 4
4 5
I i
i i
i 4
J 1
i' i
4 i
i 1
WATERFORD - UNIT 3 6-19 AMENDMENT NO. 68 4
i i
. _ = _
i ADMINISTRATIVE CONTROLS PROCESS CONTR01 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 i
the approval of the Plant Manager.
I
)
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 ODCM:
j a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p.
This document shall contain:
i 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 af ter 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 Semiannual Radioactive Effluent Release Report for the period of the 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.
4 t
WATERFORD - UNIT 3 6-24 AMENDMENT NO. 68
M M
h
- i 4
e s
i i
9 i
i i
h e
' i i
f e
i s
F f
I e
d 4
h F
l NPF-38-138 ATTACHMENT B i
t t
)
' I l
s I
i t
a 6
s y
i h
l
t j
-DEFINITIONS IDENTIFIED LEAKACE (Continued) b.
Leakage into the containment atmosphere from sources that are both i
specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or c.
Reactor Coolant System leakage through a steam generator to the f
secondary system.
MEMBER (S) OF 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
'l 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, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCUIATION MANUAL (ODCN) 1.16 The OFFSITE DOSE CALCUIATION MANUAL (ODCM) 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 Radio-l active Effluent Controls and Radiological Environmental Monitoring Frograms required by section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Esiiid Annual REMOVE i
Radioactive Effluent Release Reports required by Specification 6.9.1.7"and
.6.9.1.8.
t OPERABLE - OPERABILITY i
t
-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, l
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 l
1.18 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.2.
i i
WATERFORD - UNIT 3 1-4 Amendment No. 68 i
ii s
j
.i i
a ADMINISTRA'fIVE CONTROIS
$T ANNUAL RADIOACTIVE EFFI1rDE_XELEASE_RIfQEI REMOVE 6.9.1.8 The G5st Annual Radioactive Effluent Release Report covering the REMOVE op2 ration of the' unit during the previous 4 12 months of operation shall be REPLACE submitted within 60 days after January 1 E '.;7S'f;3 of each year. The report REMOVE shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid caste released from the unit. The material provided shall be (1) consistent with the objectives outline in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.E.1 of Appendix I to 10 CFR Part 50.
l i
l i
i l
l 4
VATERFORD - UNIT 3 6-19 AMENDMENT 68 L
6
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.
Shall become effective after review and acceptance by the PORC and the approval of the Plant Manager.
6.14 0FFSITE DOSE CALCULATION MANUAL (ODCN 1 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.3p.
This document shall containe 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 ODCE as a part of or concurrent with the S+mi Annual Radioactive Effluent Release Report for the period of the REMOVE 6 port 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.
f BATEPJORD - UNIT 3 6-24 AMENDMENT NO.68 7
i t
a
RADIOACTIVE EFFLUENTS LIOUID BOLDUP TANKS LINITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each of the following unprotected 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 te=porary storage tanks, the curie content shall be limited such that a rupture vill not result in exceeding 10 CFR Part 20 limits at the i
UNRESTRICTED APIA boundary.
- a. FWST
- b. Outside temporary tank APPLICABILITY: At all times.
ACTION :
a.
With the quantity of radioactive material in any of the above listed i
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,M Annual Radioactive Effluent Release and describe the events leading to this condition in the next Se REMOVE Report.
b.
The provision of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILIANCE REOUIRENFNTS 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 of the tank's contents at least once per 7 days when i
radioactive materials are being added to the tank.
- Based on 80% tank capacity and a MFC of 2 x 10- Ci/mL Cesium-137 equivalent, 10 CFR Part 20, Appendix B, Table II.
i T
WATERFORD - UNIT 3 3/4 11-8 8