ML19309G728
| ML19309G728 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/23/1980 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19309G723 | List: |
| References | |
| TAC-42054, NUDOCS 8005070458 | |
| Download: ML19309G728 (24) | |
Text
8005070457 P
O TECHNICAL SPECIFICATION CHANGE REQUEST NO. 62 (APPENDIX B)
Delete and add as indicated the following pages in Appendix B:
Appendix B Delete Add 1
1 11 ii (Intentionally blank) iv iv 1-1 1-1 1-2 1-2 1-3 1-4 2-1 2-1 2-2 2-2 (Intentionally blank) 2-3 2-3 (Intentionally blank) 2-4 2-4 3-1 3-1 3-2 3-2 (Intentionally blank) 3-3 3-3 (Intentionally blank) 3-4 3-4 (Intentionally blank) 3-5 3-5 (Intentionally blank) 3-6 3-6 3-7 3-7 (Intentionally blank) 4-1 4-1 4-2 5-6 5-6 5-7 5-7 5-10 5-10 5-11 5-11 5-12 Proposed Change a.
Page 1:
This page is revised to indicate the deletion of the nonradiological environmental technical specifications.
Techni-cal Specification Change Requests No. 3, dated July 21, 1977, and No. 33, dated September 22, 1978, proposed changes to the infor-mation contained on Page i.
b.
Page 11: See Item a above.
c.
Page iv: See Item a above.
d.
Page 1-1:
See Item a above.
The portion of Page 1-1 which had contained changes proposed in Technical Specifications Change Re-quest No. 40, dated May 23, 1979, is deleted in this Change Request.
e.
Page 1-2: See Item a above.
f.
Page 1-3:
This page is removed as a result of the deletion of the nonradiological environmental technical specifications.
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TECHNICAL SPECIFICATION CHANGE REQUEST NO. 62 (APPENDIX B) (Cont'd)
Proposed Change (Cont'd) 9 Page 1-4: See Item f above.
h.
Page 2-1: See Item a above.
i.
Page 2-2: See Item a above.
j.
Page 2-3: See Item a above.
k.
Page 2-4: See Item a above.
1.
Page 3-1: See Item a above.
m.
Page 3-2: See Item a above.
n.
Page 3-3: See Item a above.
o.
Page 3-4: See Item a above.
p.
Page 3-5: See Item a above.
q.
Page 3-6: See Item a above.
r.
Page 3-7:
See Item a above.
s.
Page 4-1:
See Item a above.
Technical Specification Change Re-quest No. 33, dated September 22, 1978, proposed changes to Page 4-1.
t.
Page 4-2:
See Iten f above.
Technical Specification Change Re-quest No. 33, dated September 22, 1979, had proposed removing Page 4-2.
u.
Page 5-6:
See Item a above.
~
v.
Page 5-7:
See Item a above.
Technical Specification Change Request No. 33, dated September 22, 1978, proposed changes to this page.
w.
Page 5-10: See Item a above.
x.
Page 5-11: See Item a above.
y.
Page 5-12: See Item f above.
Reason for Proposed Change This Change Request is made to eliminate the duplication of nonradiological surveillance requirements in Appendix B and in Permits No. 1009-2527 and No. FL0000159.
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TECHNICAL SPECIFICATION CHANGE REQUEST NO. 62 (APPENDIX B) (Cont'd)
Evaluation of the Environmental Impact of the Proposed Change There will be no environmental impact associated with this Change Re-quest.
The surveillance, which presently is performed in accordance with the nonradiological surveillance requirements of Appendix B, will continue to be performed in accordance with Permits No. 1009-2527 and No. FL0000159.
Benefit - Cost Analysis of the Proposed Change There will be no cost to the environment associated with this Change Re-quest since the surveillance will continue to be performed in accordance with Permits No. 1009-2527 and No. FL0000159.
The benefits associated with this Change Request include elimination of the duplication in Appendix B of requirements which are also contained in. Permits No. 1009-2527 and No. FL0000159.
In addition, enactment of this Change Request would result in the removal of confusing or, in some instances, conflicting conditions existing in such a situation where the same re-quirements are included in separate regulatory documents.
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a TSCRN62(DN92) -
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TABLE OF CONTENTS Page No.
1.0 DEFINITIONS 1.1 Frequency 1-1 1.2 Gross (p,y) Analysis 1-1 1.3 Known Radioactive Source 1-1 1.4 Intake Area 1-1 1.5 Discharge Area 1-1 1.6 Channel Calibration 1-1 1.7 Channel Check 1-2 1.8 Channel Functional Test 1-2 1.9 Dose Equivalent I-131 1-2 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 Thermal 2-1 2.2 Hydraulic 2-1 2.3 Chenical 2-1 2.4 Radioactive Effluents 2-4 2.4.1 Liquid Waste Effluents 2-5 2.4.2 Gaseous Waste Effluents 2-9 2.4.3 Solid Waste Handling and Disposal 2-16 3.0 ENVIRONMENTAL SURVEILLANCE l
3.1 Nonradiological Surveillance 3-1 3.2 Radiological Environmental Monitoring 3-6 3.2.1 Milk and Green Leafy Vegetables Census 3-26 3.2.2 Media Other Than External Radiation 3-27 3.2.3 External Radiation 3-27 3.2.4 Milk and Green Leafy Vegetables 3-27 4.0 SPECIAL SURVEILLANCE, RESEARCH, OR STUDY ACTIVITIES 4-1 5.0 ADMINISTRATIVE CONTROLS 5.1 Organization 5-1 5.2 Responsibility 5-1 5.3 Review and Audit 5-1 5.4 Action to be Taken if Limiting Condition for Operation is Exceeded 5-5 5.5 Procedures 5-5 5.6 Plant Reporting Requirements 5-6 5.6.1 Routine Reports 5-6 5.6.2 Non-routine Reports 5-11 5.6.3 Changes E-11 5.7 Records Retention 5-11 TSCRN62(DN90)
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3.2-1 Environmental Media and Exposure Pathways 3-23 3.2-2 Offsite Sample Station Locations 3-24 3.2.3 Onsite Sample Station Locations 3-25 5.1-1 Organization for Implementing Environmental Technical Specifications 5-2 5.3-1 Organization for Independent Review and Audit 5-4 i
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1-1 1.0 Definitions The following tenns are defined for uniform interpretation of the Environmental Technical Specifications for Crystal River Unit 3.
1.1 Frequency - Terms used to specify frequency are defined as below:
Once per shift - At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Daily - At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Weekly - At least once per 7 days Monthly - At least once per 31 days.
Quarterly - At least once per 92 days.
Semiannually - At least once per 6 months A maximum allowable extension for each surveillance requirement shall not exceed 25% of the surveillance interval.
1.2 Gross (6, y ) Analysis - Radioactivity measurements of gross beta or gross beta in conjunction with gross ganna as defined in Regulatory Guide 1.21.
1.3 Known Radioactive Source - A calibration source which is traceable to the National Bureau of Standards radiation measurement system and is capable of reproducible geometry.
1.4 Intake Area - The intake canal and all of the water area south of the north intake dike and within two miles of the west tip of the south intake dike.
1.5 Discharge Area - The discharge canal and all of the water area north of the south di scharge dike and within two miles of the north discharge dike.
1.6 Channel Calibration - The adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the pa rameter which the channel monitors.
The channel calibration shall encompass the entire channel including the sensor and alann and/or trip functions, and shall include the channel functional test.
Channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
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l 1-2 1.7 Channel Check - The qualitative assessment of channel behavior during operation by observation.
This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived fran independent instrument channels measuring the same parameter.
1.8 Channel Functional Test - The injection of a simulated signal into the channel as close to the primary sensor as practicable to verify operability including alann and/or trip functions.
1.9 Dose Equivalent I-131 - That concentration of I-131 (gCi/ gram) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, 1-133, I-134 and I-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in TID-14844.
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2-1 2.0 LIMITING CONDITIONS FOR OPERATION 2.1 THERMAL - Deleted 2.2 HYDRAULIC - Deleted 2.3 CHEMICAL - Deleted TSCRN662(DN90)
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2.4 RADI0 ACTIVE EFFLUENTS Objective:
To define the limits and conditions for the controlled release of radioactive materials in liquid and gaseous effluents to the environs to ensure that these releases are as low as reasonably achievable.
These releases should not result in radiation exposures in unrestricted areas greater than a few percent of natural back-ground exposures. The concentration of effluent discharges of radio-activities shall be within the limits specified in 10 CFR Part 20.
To ensure that the releases of radioactive material above background to unrestricted areas be as low as reasonably achievable, the follow-ing design objectives apply:
For liquid wastes:
A.
The annual dose above background to the total body or any organ of an individual from all reactors at a site should not exceed 5 mrem in an unrestricted area.
B.
The annual total quantity of radioactive materials in liquid waste, excluding tritium and dissolved gases, discharged from each reactor should not exceed 5 Ci.
For gaseous waste:
C.
The annual total quantity of noble gases above background dis-charged from the site should. result in an air dose due to gamma radiation of less than 10 mrad, and air dose due to beta radi-ation of less than 20 mrad, at any location near ground level which could be occupied by individuals at or beyond the bound-ary of the site.
D.
The annual total quantity of all radiciodines and radioactive material in particulate forms above background from all re-actors.
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4 3-1 3.0 ENVIR0f4 MENTAL SURVEILLANCE 3.1 N0f1 RADIOLOGICAL SURVEILLANCE - Deleted s
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3-6 3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING Objective The radiological environmental monitoring program will provide infor-mation which can be used to assist in assessing the type and quant'ity of radiation exposure in unrestricted areas resulti ng from plant ope ration.
Background
Preoperational radiological environmental monitoring programs, to es-tablish baseline environmental concentration values, were initiated in mid-1970.
One program was operated by the State of Florida De-partment of Health and Rehabilitative Services; another program was operated by the University of Florida.
A summary of the preoperational surveillance results is shown in Table 3.2-1.
This summary includes median values of the observed environmental concentrations and 95 percentile values (i.e., values which exceed 95 percent of all the comparable measured values). These values will be taken as the preoperational baseline concentrations.1 some cases the values listed are smaller than the Lower Limit of Detection (LLD).
The 95 percentile values indicate the random frequency of high measure values during the operation of the plant contributes negligibly to the environmental radioactivity. These 95 percentile values will be used during operation to assess the probability that any observed high concentration value is due to random fluctuations in measurements rather than to a true incrase in environmental concentrations.
Specification (Program)
Environmental media which are sampled and analyzed for radioactivity are shown by the two diagrams on Figure 3.2-1.
Each box in the diagrams contains the name of an environmental media which is sampled.
The upper diagram shows the critical pathways; the lower diagram shows the other monitored pathways.
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4-1 4.0 SPECIAL SURVEILLANCE, RESEARCH, OR S UDY ACTIVITIES Deleted i
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5-6 5.5.3 Prior to special tests or changes:
a.
If the Nuclear Plant Manager decides to make a change in the facility or Operating Procedures, or to conduct a test or ex-periment, and concludes that the proposed change, test, or experiment does not involve a change in the Environmental Technical Specifications or an unreviewed environmental impact question, he may order the change, test or experiment to be made, shall enter a description thereof in the operat-ing recordsof the facility, and shall send a copy of the instructions pertinent thereto to the Chairman of the Nuclear General Review Committee for review per Section 5.3.8.
b.
If the Nuclear Plant Manager desires to make a change in the facility or Operating Procedures, or to conduct a test or experiment which in his opinion might involve a change in the Environmental Technical Specifications, or involve an unre-viewed environmental impact question, he shall not order such change, test or experiment until he has referred the matter to the Nuclear General Review Committee for review and report to the Senior Vice President Engineering and Construction for resolution.
5.6 PLANT REPORTING REQUIREMENTS 5.6.1 Routine Reports A.
Annual Environmental Operating Report Amendment No. 25 TSCRN62(DN90)
5-7 Radiological Volume A report on the radiological environmental surveillance programs for the previous 12 months of operation shal' be submitted to the Director of Inspection and Enforcement (wich copy to Director, Office of the Nuclear Reactor Regulation) within 90 days after January 1 of each year.
The period of the first report shall be-gin with the date of initial criticality.
The report shall in-clude summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activi-ties for the report period, including a comparison with preopera-tional studies, operational controls (as appropriate) and previous environmental surveillance reporto, and an assessment of the ob-served impacts of the plant operc. tion on the environment.
If harmful effects or evidence of irreversible damage are detected by the monitoring, the licensee shall provide an analysis of the problem and a proposed course of action to alleviate the problem.
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Deleted C.
Radiological Reporting Levels In the event a report level specified below is reached, a report shall be made within the designated time period to the Director of Inspection and Enforcement with a copy to the Director of Office of Nuclear Reactor Regulation.
(1) Radioactive Discharge If measured rates of release of radioactivity in the environ-ment, averaged over a calendar quarter, exceed the design objective rates as specified in specifications 2.4.1.H for liquid effluents and in 2.4.2.C for airborne effluents, a re-port of the causes of the release rates and of a proposed program of action to reduce the release rates will be sub-mitted with 30 days fran the end of the quarter during which the release occurred.
(2) Radiological Environmental Monitoring If a single measured value of radioactivity concentrations in critical pathway environmental medium samples identified in Section 3.2 exceeds ten times the control station value as defined in Section 3.2, a written notification including an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous result shall be submitted to the Directo;' of the NRC Regional Office (with a copy to the Director, Office of Nuclear Reactor Reg-ulation) within 10 days after confirmation.*
- Confirmation is defined in Regulatory Guide 4.8.
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5-11 5.6.3 Changes A.
A report shall be made to the Director of Office of Nuclear Reactor Regulation prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have, in the judgement of the applicant, a significant adverse effect on the environ-ment or involves an environmental matter or question not pre-viously reviewed and evaluated by the USNRC.
The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.
B.
Request for changes in environmental technical specifications shall be submitted to the Director of Office of Nuclear Reactor Regulation for review and authorization.
The request shall include an evaluation of the impact of the change and a supporting benefit-cost analysis.
5.7 RECORDS RETENTION 5.7.1 Records and logs relative to the following areas shall be retained for the life of the plant:
a.
Records and drawing changes reflecting plant design modifi-cations made to systems and equipment as described in Section 5.6.3.
b.
Records of environmental surveillance data.
c.
Records to demonstrate compliance with the limiting condi-tions for operation in Section 2.0.
5.7.2 All other records and logs relating to the environmental technical specifications shall be retained for five years.
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