ML20094F422
| ML20094F422 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/03/1995 |
| From: | Hall J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20094F427 | List: |
| References | |
| NUDOCS 9511080338 | |
| Download: ML20094F422 (14) | |
Text
,
pn Mou e e-t UNITED STATES g
,g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 01 os...../
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 i
COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.172 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated December 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by 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; D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
f i
9511080338 951103 PDR ADOCK 05000298 1
p PDR
4 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby d
amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.172, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
i Ja e R. Hall, Senior Project Manager Pro ect Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 3, 1995 4
4
ATTACHMENT TO LICENSE AMENDMENT NO. 172 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET N0. 50-298 I
1 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES iv iv 216n 216n 216s 216s 216al 216a1 216a3 216a3 216a9 216a9 216al2 216a12 230 230 231 231 232 232 235b 235b
~.
TABLE OF CONTENTS (Cont'd. )
Page No.
SURVEILLANCE LIMITING CONDITIONS FOR OPERATION REOUIREMENTS 6.2 Review and Audit 220 6.2.1.A Station Operations Review Committee (SORC) 220 A.1 Membership 220 A.2 Meeting Frequency 220 A.3 Quorum 220 A.4 Responsibilities 220 A.5 Authority 221 A6 Records 221 A.7 Procedures 221 6.2.1.B NPPD Safety Review and Audit Board (SRAB) 222 B.1 Membership 222 B.2 Meeting Frequency 222 B.3 Quorum 222 B.4 Review 222 B.5 Authority 223 B.6 Records 223 B.7 Audits 223 6.3 Procedures and Programs 225 6.3.1 Introduction 225 6.3.2 Procedures 225 i
6.3.3 Maintenance and Test Procedures 225 j
6.3.4 Radiation Control Procedures 225 l
.A High Radiation Areas 226 l
6.3.5 Temporary Changes 227 i
6.3.6 Exercise of Procedures 227 1
6.3.7 Programs 227 j
.A Systems Integrity Monitoring Program 227 i
.B Iodine Monitoring Program 227
.C Post-Accident Sampling System (PASS) 227 6.4 Record Retention 228 l
6.4.1 5 year retention 228 6.4.2 Life retention 228 i
6.4.3 2 year retention 229 i
6,5 Station Reporting Requirements 230 s
6.5.1 Routine Reports 230
.A Introduction 230
.B Startup Report 230 i
.C Annual Reports 230
.D Monthly Operating Report 231
.E Annual Radiological Environmental Report 231
.F Annual Radioactive Materials Release Report 232 l2'
.G Core Operating Limits Report 232 Amendment NO. 195;142,172
.tv.
_ _ =
l l
LIMITING CONDITION FOR OPERATION SURVEILIANCE REOUIREMENTS 3.21 ENVIR0! MENTAL /RADIOLDGICAL EFFLUENTS 4.21 ENVIRONMENTAL /RADIOLDGICAL EFFLUENTS A.
Instrumentation A.
Instrumentation 1.
Liquid Effluent Monitoring 1.
Liquid Effluent Monitoring Applicability:
As shown in a.
Each radioactive liquid Table 3.21.A.l.
eff1uent monitoring i
instrumentation channel shall Soecification:
be demonstrated OPERABLE by 4
performance of the CHANNEL j
a.
The radioactive liquid CHECK, SOURCE CHECK, CHANNEL eff1uent monitoring CALIBRATION and CHANNEL instrumentation channels FUNCTIONAL TEST operations shown in Table 3.21.A.1 shall during the modes and at the be OPERABLE with their alarm frequencies shown in and trip setpoints set to Table 4.21.A.l.
ensure that the limits of 3.21.B.1 are not exceeded.
b.
Radioactive liquid effluent monitor alarm and trip l
b.
With a radioactive liquid setpoints shall be determined effluent monitoring in the manner described in the 4'
instrumentation channel alarm ODAM.
j and trip setpoint less conservative than required, reset without delay to meet Specification 3.21.A.l.a.
suspend the release of radioactive liquid effluents monitored by the affected channel, declare the channel inoperable, or change the i
setpoint so it is acceptably l
conservative, c.
With less than the minimum required number of radioactive liquid effluent i
monitoring instrumentation l
channels OPERABLE, take the ACTION shown in Table 3.21.A.l.
d.
If the minimum number of instrument channels is not returned to OPERABLE status within 31 days, in lieu of any other report, explain in the next Annual Radioact.ve Materials Release Report why the instrument was not repaired in a timely manner.
e.
The provisions of Definition J are not applicable.
The reporting prov i s i ons of Specification 6.5.2 are not applicable.
Amendment NO. 89.172 216n-
4 LIMITING CONDITION FOR OPERATION SURVEILIANCE REQUIREMENTS 3.21.A (Cont'd) 4.21.A (Cont'd) 2.
Gaseous Effluent Monitoring 2.
Gaseous Effluent Monitoring Aeolicability:
As shown in a.
The setpoints shall be Table 3.21.A.2.
determined in accordance with the method described in the SpecificatioD:
ODAM.
a.
The radioactive gaseous b.
Each radioactive gaseous effluent monitoring effluent monitoring instrumentation channels instrumentation channel shall shown in Table 3.21.A.2 shall be demonstrated OPERABLE by be OPERABLE with their alarm performance of the CHANNEL setpoints set to ensure that CHECK, SOURCE CHECK, CHANNEL the limits of Specification CALIBRATION, and CHANNEL 3.21.C.1 are not exceeded.
FUNCTIONAL TEST operations during the modes and at the b.
With a radioactive gaseous frequencies shown in effluent monitoring Table 4.21.A.2.
instrumentation channel alarm setpoint less conservative than a
value which will ensure that the limits of 3.21.C.1 are
- met, reset without delay to comply with Specification 3.21.A.2.a.
declare the channel l
inoperable; IMMEDIATELY suspend release; or change the setpoint so it is acceptably conservative.
c.
With less than the minimum required number of radioactive gaseous effluent monitoring instrumentation l
channels OPERABLE, take the ACTION shown in Table 3.21.A.2.
d.
If the minimum number of instrument channels are not returned, to OPERABLE status within 31 days, in lieu of any other report, explain in the next Annual Radioactive Materials Release Report why the instrument was not repaired in a timely manner.
e.
The provisions of Definition J are not applicable.
The reporting provisions of Specification 6.5.2 are not applicable.
Amendment NO. % 172
-216s-
NOTES FOR TABLE 4.21.B.1 (Continued)
(5) A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed.
(6) A grab sample of plant service water effluent shall be analyzed at least once each week in accordance with Tabje Item 2. A.
In the event the radioactivity concentration in a sample exceeds 3 x 10 pCi/ml, or in the event the plant service water effluent monitor indicates the presence of an activity concentration greater than 6
3 x 10 pCi/ml, sampling and analysis according to Table Item 2.B. shall commence and shall be performed as long as the condition persists.
(7) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:
Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.
Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the Annual Radioactive Materials Release Report.
l (8) If an isotopic analysis is unavailable, batch releases may be made for up to 14 days provided the gross beta / gamma concentration to the unrestricted area is
$ 1 x 10'7 pc/ml and the sample is analyzed when the instrumentation is once again available.
(9) Analysis may be performed after release.
(10)
A continuous release is the discharge of liquid wastes of a nondiscrete volume; I
e.g., from a volume of system that has an input flow during the continuous release.
FREQUENCY NOTATION:
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 />.
A
- At least once per year.
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 />.
R
- At least once per 18 months.
W - At least once per 7 days.
S/U - Prior to each reactor startup.
M - At least once per 31 days.
P
- Completed prior to each release.
Q - At least once per 92 days.
NA - Not applicable.
SA - At least once per 184 days.
Amendment No. -85L,172 4164-
)
LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTS 3.21.B (Cont'd) 4.21.B (Cont'd) 2 3.
Temporary, Outside Storage 3.
Temporary, Outside Storage j
Tanks of Radioactive Liquid Tanks of Radioactive Liquid 1
I a.
In the event temporary, a.
When radioactive liquid unprotected tanks are is being added to a
used outside to store temporary, unprotected radioactive liquid, the outside storage tank, the contents of each tank liquid shall be sampled shall not exceed and analyzed for 10 curies, excluding radioactivity at least H 3 and dissolved noble once per 7 days.
gas.
b.
If the quantity of radioactive material in a
teaporary, unprotected storage tank outside exceeds 10 curies, excluding H 3 and dissolved noble
- gas, immediately suspend addition of radioactive material and begin measures to i
reduce the content to 10 curies or less without delay and describe the events l
leading to the condition in the next l
Annual Radioactive Materials Release Report.
i c.
The provisions of Definition J are not applicable.
4 4
?
3 I
i Amendment No. 44,172
-216a3-
l i
I
~
(4) Analyses shall also be performed following an increase as indicated by the gaseous 4'
release monitor of greater than 50% in the steady state release, after factoring out increases due to power changes or other operational occurrences, which could alter the mixture of radionuclides.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less are analyzed, the corresponding LLD's may be increased by a factor of 10.
l (5) The ratio of the sample flow rate to the sampled stream flow rate shall be known for j
the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.21.C.1, 3.21.C.2 and 3.21.C.3.
(6) The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe 138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.
This list does not mean that only these nuclides are to be detected and reported.
Other peaks which are measurable and identifiable, together with the above nuclides, shall also be i
identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.
When unusual circumstances cause LLD's higher than required for more than 31 days, the reasons shall be documented in the Annual Radioactive Materials Release Report.
l l
(7) A quarterly composite particulate sample shall include a portion of each weeks particulate samples collected during the quarter.
(8) The noble gas continuous monitor shall be calibrated using laboratory analysis of the j
grab samples from A and B on Table 4.21.C.1 or using reference sources.
(9) A H-3 grab sample will also be taken when the reactor vessel head is removed. This sample will be taken at the ERP or Reactor Building vent whichever will be representative dependent upon the head removal vacuum procedure.
i j
FREQUENCY NOTATION:
i j
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 />.
]
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 />.
W At least once per 7 days.
M At least once per 31 days.
Q At least once per 92 days.
3 EA At least once per 184 days.
A At least once per year.
=
R At least once per 18 months.
S/U Prior to each reactor startup.
P Completed prior to each release.
NA Not applicable.
1 l
i H
a I
Amendment No. 4M),172 216a9-t
LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENTl e
3.21.D (Cont'd) 4.21 (Cont'd) information specified in 40 CFR Part 190.11(b) is included. In that event, a variance is granted until NRC Staff action on the item is complete.
2.
The provisions of Definition J sre not applicable.
E.
Solid Radioactive Vaste E.
Solid Radioactive Vaste Aeolicabiliev:
During solid 1.
Operating parameters and radwaste processing.
limits for the solidification of radioactive waste were Specification:
established during preparational testing of the 1.
The appropriate equipment of system.
Radioactive waste the solid radwaste system solidification shall be shall be operated to process performed in accordance with radioactive waste containing established parameters and liquid and liquid destined limits.
In addition, every for disposal subject to 10 10th batch of dewatered waste CFR Part 61 to a form that will be sampled prior to meets applicable requirements solidification and analyzed of 10 CFR Part 61.56 before for pH.
the waste is shipped from the site.
2.
Each drum of solidified or dewatered radioactive waste 2.
Suspend delivery to a carrier will be inspected, prior to for transport of any capping, to insure that there container of waste subject to is no free standing liquid on Specification 3.21.E.1 which top of the solid waste.
does not comply with 10 CFR Part 61.56.
3.
The Annual Radioactive Materials Release Report in Specification 6.5.1.F shall include the following information for radioactive solid waste shipped offsite during the report period:
Amendment No. -84,172
-216a12-
\\
i 6.5 STATION REPORTINC REOUIREMENTS e
6.5.1 Routine Reports l
A.
Introduction - In addition to the applicable reporting requirements of Title 10, code of Federal Regulations, the following identified reports shall be submitted to the individual (s) designated in the current i
revision of Reg. Guide 10.1 unless otherwise noted.
B.
Startup Report 1.
A summary report of plant startup and power escalation testing shall be submitted following:
a.
Receipt of an operating license.
b.
Amendment to the license involving a planned increase in power level.
c.
Installation of fuel that has a different design or has been manufactured by a different fuel supplier.
d.
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 FSAR
)
and shall include a description of the measured values of the j
operating conditions or characteristics obtained during the test J
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.
2.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If all three events are not completed, supplementary reports shall be submitted every three months.
C.
Annual Reports Routine reports covering the subjects noted in 6. 5.1. C.1, 6.5.1.C.2, 6.5.1.C.3_ and 6.5.1.C.4 for the previous calendar year shall be submitted prior to May 1 of each year.
i t
l Amendment No. 4 3,41,80,82, 172
-230-
- y 1
=
6.5.1.C (Cont'd) 1.
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions,1/ e.g., reactor operations and surveillance, inse rvice 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,
- TLD, or film badge measurements.
Small exposures totaling 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 maj or work functions.
2.
A summary description of facility changes, tests or experiments in accordance with the requirements of 10CFR50.59(b).
This report may be submitted annually or along with the Updated Safety Analysis Report (USAR) updates as required by 10CFR50.71(e).
3.
Pursuant to 3. 8. A, a report of radioactive source leak testing.
This report is required only if the tests reveal the presence of 0.005 microcuries or more of removable contamination.
4.
Locumentation of all challenges to relief valves or safety valves.
l D.
Monthly Operatine Report i
Routine reports of operating statistics, shutdown experience, and a narrative summary of operating experience relating to safe operation of the facility, shall be submitted on a monthly basis in the manner specified by 10CFR50.4 no later than the 15th of each month following the calendar month covered by the report.
i E.
Annual Radiolocical Environmental Report 1.
Routine radiological environmental reports covering the surveillance activities related to the Station operation during the previous calendar year shall be submitted to the NRC before May 1 of each year.
2.
The Annual Radiological Environmental Report shall include the following:
a.
A summary of doses to a Member of the Public Offsite due to Cooper Station aqueous and airborne radioactive effluents, calculated in accordance with methods compatible with the ODAM.
b.
A summary of the results of the land use census required in Specification 4.21.F.2.
1/
This tabulation supplements the requirements of $20.407 of 10CFR Part 20.
Amendment No. 87,80,100,149,172
-231-
9 6.5.1.E (Cont'd) c.
Summarized and tabulated results in the format of Table 6.5 1 of analyses of samples required by the radiological environmental monitoring program, and taken during the report period.
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
d.
A summary description of the radiological environmental monitoring program including any changes; a map of all a table giving distances and sampling locations keyed to directions from the reactor; and the results of participation in the Inter-laboratory Comparison Program, required by Specification 3.21.G.
F.
Annual Radioactive Materials Release Report l
1.
A report of radioactive materials released from the Station during the preceding year shall be submitted to the NRC by May 1 of each l
year.
2.
The Annual Radioactive Materials Release Report shall include the l
following:
a.
A summary by calendar quarter of the quantities of radioactive liquid and gaseous effluents released from the Station.
The data should be reported in the format recommended in Regulatory Guide 1.21, Appendix B Tables 1 and 2.
b.
A summary of radioactive solid waste shipped from the
- Station, including information named in Specification 4.21.E.3.
c.
A summary of meteorological data collected during the year shall be included in the Annual Report submitted by May 1 of l each year.
d.
A list and brief description of each unplanned release of gaseous or liquid radioactive effluent that causes a limit i
in Specification 3.21.B.1.a, 3.21.B.2.a.
3.21.C.l.a.
3.21.C.2.a, or 3.21.c.2.a to be exceeded.
e.
Calculated offsite dose to humans resulting from the release of effluents and their subsequent dispersion in the atmosphere reported in accordance with Regulatory Guide 1.21.
6.5.1.C Core Operatine Limits Reoert Core operating limits shall be established and documented in the Core Operating Limits Report prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
a.
The Average Planar Linear Heat Generation Rates (APLHGR) for Specification 3.11.A.
Amendment No. -8914&,172 7
-232-
e 6.6 Process Control Program (PCP) 6.6.1 The PCP shall be a manual detailing the program of sampling, analysis and formulation determination by which SOLIDIFICATION of radioactive vaste from liquid systems is assured consistent with Specification 3.21.E and the surveillance requirements of these Technical Specifications.
6.6.2 District Initiated Chances A.
Shall be submitted to the Commission by inclusion in the Annual Radioactive Materials Release Report for the period in which the change (s) was made effective and shall contain:
1.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information; 2.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and 3.
Documentation of the fact that the change has been reviewed and found acceptable by the SORC.
B.
Shall become effective upon review and acceptance by the SORC.
6.7 Offsite Dose Assessment Manual (ODAM) 6.7.1 The ODAM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications.
The ODAM also describes the Environmental Radiation Monitoring Program.
6.7.2 District Initiated Chances A.
Shall be submitted to the Commission by inclusion in the Annual Radioactive Materials Release Report for the period in which the change (s) was made effective and shall contain:
1.
Sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information. Information submitted should consist of a package of those pages of the ODAM to be changed with each page numbered and provided with a signed approval and date box, together with appropriate analyses of evaluations justifying the change (s).
2.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations.
3.
Documentation of the fact that the change has been reviewed and found acceptable by the SORC.
B.
Shall become effective upon review and acceptance by the SORC.
Amendment NO. -84,172
-235b-
-