ML13316A620
| ML13316A620 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 06/04/1984 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML13316A619 | List: |
| References | |
| DPR-13-A-076 NUDOCS 8406070261 | |
| Download: ML13316A620 (23) | |
Text
41 UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SOUTHERN CALIFORNIA EDISON COMPANY AND SAN DIEGO GAS AND ELECTRIC COMPANY DOCKET NO. 50-206 SAN ONOFRE NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 76 License No. DPR-13
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Southern California Edison Company and San Diego Gas and Electric Company (the licensees) dated December 5, 1983 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), 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 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 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.
8j40670617 840604 PDR ADOCK 0 0000 PPDD
-2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No.
DPR-13 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 76, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
-Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 4, 1984
ATTACHMENT TO LICENSE AMENDMENT NO. 76 PROVISIONAL OPERATING LICENSE NO. DPR-13 DOCKET NO. 50-206 Revise Appendix B Environmental Technical Specifications by removing the following pages and by inserting the enclosed pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
Remove Pages Insert Pages iii iii iv iv 1-1 1-1 1-2 1-2 5-7 5-7 5-7a*
5,7b*
5-7c 5-8 5-8 5-11 5-11 5-13 5-13 5-14 5-14 5-14a 5-14a 5-14b 5-14b 5-15 5-15 5-16 5-16 5-17 5-17 5-19 5-19 5-20 5-20
- There are no changes to the provisions contained on these pages; these specifications were inadvertently deleted from the TS by Amendment No. 66 and are restored by this amendment.
TABLE OF CONTENTS (Cont't)
PAGE 3.2 Radiological Environmental Monitoring.......
3-12 3.2.1 Air Sampling 3-13 3.2.2 Direct Radiation 3-14 3.2.3 Drinking Water..
- *...... 3-15 3.2.4 Ocean Water.
3-16 3.2.5 Beach Sand.
3-17 3.2.6 Local Crops.
3-17 3.2.7 Non-migratory Marine Animals.......3-19 3.2.8 Kelp..
3-20 3.2.9 Ocean Bottom Sediments......
3-21 3.2.10 Soil Sampling.
3-22 3.2.11 Jack Rabbit Sampling..........
3-23 4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES............* *
- 4-1 4.1 Chlorine (Deleted) 4.2 Fish Impingement (Deleted) 4.3 Entrainment (Deleted) 5.0 ADMINISTRATIVE CONTROLS..
5-1 5.1 Responsibility..
5-1 5.2 Organization 5-1 5.3 Review and Audit.
5-1 5.4 Action to be Taken if a Limiting Condition for Operation is Exceeded (Deletedl...
5 -7 c 5.5 Procedures 5-7c 5.6 Station Reporting Requirements..
5-8 5.6.1Routine Reports-Annual 5-8 5.6.2 Routine Reports-Semiannual.5-11 Non-Routine Reports.
5-13 5.6.4 Changes.
5-14b 5.7 Records Retention.
5-14b 5.8 Special Requirements.................
5-15 5.8.1 Intake System.........
5-15 5.8.2 Discharge System 5-1 5.8.3 Chemical Effluents (Deleted).......
5-17 5.8.4 LandManagement..
5-18 MAR 26 1981 Amendment No. V7.
76
SCHEDULE FOR IMPLEMENTATION Except as noted below, all provisions of this environmental technical specification shall be effective as of the date of issuance. The following sections shall be implemented as soon as possible, and must be effective within the time period listed.
Section Time Period for Implementation (Months after Issue Date) 2.0 LIMITING CONDITIONS FOR OPERATION 2.1.1 (Deleted) 2.1.2 (Deleted) 2.2.1 (Deleted) 3.0 ENVIRONMENTAL SURVEILLANCE 3.1 (Deleted) iii MAR 2 6 1981 Amendment No.
3 76
3.2.1 Air Sampling 1
3.2.2 Direct Radiation 1
3.2.3 Drinking ater 1
3.2.4 Ocean Water 1
3.2.5 Beach Sand 1
3.2.6 Local Crops 1
3.2.7 Non-Migratory Marine Animals
- 3.
3.2.8 Kelp 3
3.2.9 Ocean Botom Sediments 3
3.2.10 Soil Sampling 1
3.2.11 Jack Rabbit Sampling 1
4.0 SPECIAL SURVEILLANCE AND STUDY ACTIVITIES 4.1 Deleted 5.0 ADMINISTRATIVE STANDARDS 1
5.6.1 The first Semi-annual Report as required by Section 5.6.1 shall be submitted within 90 days after July 1, 1975.
Amendment No. 76 iv
1.0 DEFINITIONS 1.1 Bimonthly Once every two months + one week.
1.2 Quarterly Once every three months + two weeks.
1.3 Semiannually Once every six)months + one month.
1.4 Station San Onofre Nuclear Generating Station Unit 1.
15 (Deleted) 1.6 Circulating Water System The system which provides ocean cooling water for the main condensers, turbine plant cooling water heat exchangers and component cooling water heat exchangers. It includes the conduits, screen well, gates, valves, and other appurtenances.
1.7 Cooling Water Ocean water used in the circulating water system for Station cooling.
1.8 Discharge Temperature The temperature of the cooling water as measured in the discharge conduit near the tsunami wall.
1.9 Intake Temperature The temperature of the cooling water as measured in the intake conduit near the tsunami wall.
1.10 ETS Environmental Technical Specificationg Amendment No. 76
1.11 Heat Treatment The use of elevated water temperatures for control of fouling organisms in the circulating water system.
1.12 (Deleted) 1.13 (Deleted)
-1.14 (Deleted) 1-2 DEC 1 9 1975 Amendment No. 76
5-7 5.3.1.14 The Station Manager shall assure the performance of a review by a qualified individual/organization of every uncontrolled or unplanned release of radioactivity to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Manager of Nuclear Operations and to the Chairman of the NARC.
5.3.1.15 Reports documenting each of the activities performed under Specifications 5.3.1.9 through 5.3.1.14 shall be maintained. Copies shall be provided to the Manager of Nuclear Operations and the Chairman of the MARC."
Amendment No. 6 76
,5-7a 5.3.2 The membership of the Nuclear Audit and Review Comittee and the responsibilities and authorities of the Committee with respect to these environmental technical specifications are as follows:
- a.
Membership (Chairman designated by the Nuclear Control Board)
(1)
Manager of Engineering Design (2)
Manager of Environmental Affairs (3)
Manager of Nuclear Engineering, Safety & Licensing (4) Manager, Nuclear Engineering & Safety I
(5)
Manager, Biological Systems Research and Development (6) Manager, Quality Assurance (7) Manager of Nuclear Operations (8) San Diego Gas & Electric Representatives
- b. Resoonsibilities (1) Review and investigate reports concerning violations of the Environmental Technical Specifications.
Where investigation indicates, evaluate and prepare recom mendations to prevent their recurrence.
(2)
Review proposed changes to the Environmental Techni cal Specifications.
Coordinate environmental technical specifications with the safety technical specifications to avoid conflicts and maintain consistency.
Submit approved proposed changes to the Environmental Technical Specifications to the Nuclear Control Board for transmittal.
- 3) Review and approve proposed changes to the facility and its procedures or proposed tests or experiments which are forwarded by the Onsite Review Committee when they involve r change in the Environmental Technical Specifications, or a change which would significantly alter the environmental inpact of the facility.
Submit such proposed changes when required with appropriate environmental analysis to the Nuclear Control Board for Transmittal.
(4)
Review all environmental surveillance programs for compliance with these environmental technical specifications.
(5)
Review all. design changes related to changes in the Station which relate to the environmental impact of the station and its operation.
(6)
Review overall facility activities as they relate to environmental impact by:
(a) formal facility review annually and as directed by the Cmittee Chairman.
(b) review of Dnsite Review Comittae meeting minutes.
Amendment No.
76 May. 7, 1981
(g
-"(5-lb c) review of reportable environmental occurrences, and other environmental impact-related facility incident reports.
(d) ensure that results of the environental surveillance programs are revfewed prior to their submittal in each semiannual operating report.
(7) When deficiencies in the ad8inistrative controls for the facility in relation to environmental effects are determined through the review of the Comittee, corrective action shall be initiated by the Chairman and a report submitted to the Nuclear Control Board.
- c.
Meetinz Freauencv:
Semiannualiv and as Reauired
- d.
uoru:
The chairman or his designated alternate and four members knowledgeable in environmental matters.
Alternates:
Alternate rmbers shall be appointed in writing by the Nuclear Audeit and Review Committee Chairman to serve on a temporary basis; however, no more than two alternates shall participate in Nuclear Audit and Reviev Committee actions at any time.
5.3.3 The membership of the Nuclear Control Board and its responsibilities and authorities with respect to these environmental technical specifications are as follows:
- a.
Membershiv:
(1)
Vice President (Nuclear Engineering & Operations)
(2) Vice President (Advanced Engineering)
(3) Vice President (Engineering and Construction)
(4) Vice President (San Diego Gas & Electric Company)
- 0.
Resconsibilities (1)
Formally submit an environmental analysis report to the NRC if an environmental technical specification is violated.
(2)
Formally submit proposed changes to the Environmental Technical Specifications and design or operational changes which would significantly alter the environ mental impact of the facility to the NEC for final approval.
(3)
Maintain management control with respect to environmental impact.
- c.
Meetin2 Frecuencr:
As Reuired
- d.
uoru:
Two Amendment No..,
76 dune 25, 1980
5-7c The function and responsibilitY of the Quality Assurance Organization relative to verification of compliance with these environmental technical specifications are as follows:
- a.
Function:
To provide assurance that activities involved in carrying out..these e=vironmental technical specifica tions are performed in accordance with specification.
requirements through audits and surveillance as provided by the program required by Section 5.1.
- b.
Resonsibilities:
(1)
Periodic audit of the records of activities which have been performed.
(2)
Surveillance on a selected basis of activities as they are being performed.
(3) erification of the established and maintenanceof the procedures required by Section 5.5 and of the overall program description required by Section 5.1.
,4 Action to Be Taken If a Lirnitenc Condition For Oeration Is Exceeded (Deleted)
-. 5 Procedures 5.5.1
'Pritten procedures, including applicable checklists and instructions, shall be prepared and followed for the activities involved in carrying out these eawirommental technical specifications.
Procedures sba.U imrclude sampling, data recording and storage, instrument calibration, measur ments and analyses, testing frequency of a=y alarms and actions to be taken when limits are approached or exceeded.
Procedures shall be prepared for assuring the quality of program results, including analytical measurements, and which:
document the program in policy directives; designate a responsible organization or individuals; include purchased services, e.g., contractual lab or other contract services; incclude audits by licensee personnel; and include systems to identify and correct deficiencies, investigate anamalous or, suspect results, and review and evaluate program results and reports.
Amendment No. 76
5.5.2 (Deleted) 5.6 Station Reporting Requirements The following information shall be submitted to the USNRC in addition to the reports required by Title 10, Code of Federal Regulations.
5.6.1 Routine Reports -
Annual A report on environmental surveillance programs for the previous year of operation shall be submitted as part of the Annual Operating Report prior to March 1 of each year.
The report shall be a summary and interpretation of the results of the environmental activities for the period, including where available a comparison with preoperational studies, and an assessment of the observed impacts of the plant operation on the environment. The report shall contain but not be limited to the following:
- a.
Maintenance A discussion of corrective maintenance (excluding preventative maintenance) performed during the reporting period on systems and components that control, reduce or prevent the release of radioactive materials to the environs.
For any malfunctions for which corrective maintenance was required, information shall be provided on:
(1) the system or component involved, (2) the cause of the malfunction, (3) the results and effect on plant operation, (4) corrective action taken to prevent repetition, and (5) special precautions taken to provide for environmental protection during repair.
- b.
Changes, Tests, and Experiments A brief description and a summary of the environmental impacts of those changes, tests, and experiments which were carried out without prior Commission approval.
Also, changes or additions to permits and certificates required by Federal, State, local and regional authorities for the protection of the environment will be reported. The submittal will include an evaluation of the environmental
- impact of the change.
5-8 DEC 195
~Amendment No. 76
r '
d4.
Oceanograpl and Biological EnvironSmentaonitoring (Deleted) 5.6.2 Routine Reports -
Semiannual Within 60 days after January 1 and July 1 of each year a-.
report shall be submitted covering the radioactive content of effluents released to unrestricted areas and shipments of solid waste during the previous six months of operation. The data shall be summarized on a monthly basis and shall include as a minimum the following:
- a.
Radioactive Effluent Releases A statemeht of the quantities of radioactive effluents released from the station with data summarized on a monthly basis following the format of USAEC Regulatory Guide 1.21.
(1) Gaseous Effluents (a) Gross Radioactivity Releases
- i. Total gross radioactivity (in curies), primarily noble and activation gases.
ii. 'Maximum gross radioactivity release rate during any one-hour period.
5-11 1 Amendment No.
7
-NOY5 -I2M0
) Total tritium and total al a radioactivity (in curies) released and average concentra tion released to the unrestricted area.
(d) Total dissolved gas radioactivity (in curies) and average concentration released to the unrestricted area.
(e) Total volume (in liters) of liquid waste released.
(f) Total volume (in liters) of dilution water used prior to release from the restricted area.
(g) Total gross radioactivity (in curies) by nuclide released based on representative isotopic analyses performed.
(h) Percent of Technical Specification limit for total radioactivity.
'b. Solid Waste (1) The total amount of solid waste shipped (incubic feet).
(2) The total estimated radioactivity (in curies) involved.
(3) Disposition including date and destination.
5.6.3 Non-Routine Reports
- a. Prompt Notification With Written Followup The types of events listed below shall be reported as expeditiously as possible, but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Regional Administrator or his designeL, no later than the first working day following the event.
A written followup report shall be submitted to the Regional Administrator (with copy to the Office of Director, Nuclear Reactor Regulation)within two weeks of the event.
5-13 DC 1 t 175 Amendment No. 76
The written report and to the extent possible the preliminary telephone and telegraph report, will:
(a) describe, analyze, and evaluate the occurrence, including extent and magnitude of the impact, (b) describe the cause of the occurrence and indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components of systems.
In the event a reporting level is reached, reports shall be submitted as set forth in the applicable specifica tion to the Regional Administrator and to the Director, Office of Nuclear Reactor Regulation.
(1) 1 (Deleted)
(2) An uncontrolled or unplanned release of radio activity from the Station.
- b. Thirty-Day Written Report The reportable occurrences listed below shall be the subject of written reports to the Regiona Adintrat +rn
--Rginal Admi...
with copy to the-Director. Office of Nuclear Reactor Requlation within thirty days of occurrence of the event. The report will: (a) describe, analyze, and evaluate.the occurrence, includ'ing extent and magnitude of the impact, (b) describe the cause of the occurrence and indicate the corrective action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences involving similar components of systems.
(1) Discovery of any substantial variances in the environmental impact analyses established in the Environmental Report.
(2) Discovery of any substantial variance in environmental impact or design features described in the Environmental Report or the Environmental Technical Specifications.
(3) Instances where primary data collection systems required by Environmental Technical Specifications in Sections 3 and 4 are inoperative, or the data collected are lost or invalid or cannot be 5-14 Amendment No. 76
tained due to severe weather similar onditions, for the following piods (unless corrective measures are taken to recover or restore the required data):
(a) Continuous-monitoring data one week continuous or a total in excess of three weeks per year.
(b) Weekly monitoring data -
two successive weeks or a total in excess of three weeks per year.
(c) Monthly, bimonthly, quarterly, and semiannual monitoring data -
one sample per year.
()
Vlioleted)
(5)
(Deleted)
- e. Environmental Surveillance Reports In the event a reporting level is reached, reports shall.
be made as set forth in the applicable specification.
Such reports shall be submitted in writing to the Regional Administrator and to the Director, Office of Nuclear Reactor Regulation.
- d. Special Reports Special reports shall be submitted in writing within 90 days to the Director, Office of Nuclear Reactor Regulation, USNRC, Washington, D. C. 20M55.
The frequency and content of these special reports are determined on an individual case basis and are designated in these Environmental Technical Specifications.
5-14a Amendment No. 76
5.6.4 Changes
- a. A report shall be made to the NRC 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 a significant adverse effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the NRC. The report shall include a description and evaluation of the change and a supporting benefit-cost analysis.
- b. Request for changes in environmental technical specifica tions-shall be submitted to the Director, Office of Nuclear
.Reactor Regulation, USNRC, for review and authorization.
The request shall include an evaluation of the impact on the change and a supporting benefit-cost analysis.
5.7 Records Retention 5.7.1 Records and logs relative to the following items shall be kept in a manner convenient for review and retained for.the life of the plant.
- a. Records, including but not limited to periodic checks, inspections and/or calibrations to verify that requirements specified under environmental monitoring requirements are being met.
5-14b DECe nN 7
Amendment No. 76
- b.
Records of all environmental surveillance data required to show compliance with these environmental technical specifications.
- c.
Records and drawings detailing plant design changes and modifications made to systems and equipment as described in Section 5.6.4.
5.7.2 All-other records and logs relating to those environmental technical specifications shall be retained for a period of not less than 5 years. These shall include (but are not limited to) the following:
- a.
Details of any abnormal operating conditions having an effect on the environment, and actions taken to correct those conditions.
- b.
Maintenance activities to environmentally-related equipment, including but not limited to:
(1) routine maintenance and component replacement, (2) equipment failures, (3) replacement of principal-items of 'equipment.
- c.
Off-site radiological environmental monitoring surveys.
- d.
Records of radioactivity levels in liquid and gaseous wastes released to the environment.
- e.
All reviews, including actions taken and reasons therefore, required in Sections 3 and 4 of this specification.
- 5.8 SPECIAL REQUIREMENTS This section contains a description of Station design features and operating practices which, if changed, could have a significant effect on environmental impact. Any significant change in Station design features or operating practices described herein, or which could have a significant effect on environmental impact or which reouire a change in the ETS, must be reported to the Director, Office of Nuclear Reactor Regulation in accordance with the provisions of Section 5.6.4a prior to the change.
5.8.1 Intake System The circulating water system, under normal operating conditions, draws water from the ocean at a point approximately 3200 feet offshore. The ocean bottom at this point is approximately 27 feet below mean lower low-water level. The intake structure rests on a foundation located 33 feet beneath the ocean bottom and rises vertically to a point 10-1/2 feet above the ocean Amendment No. 76
floor. The inside horizontal dimensions of the intake structure are 16 to 21 feet. A velocity cap, 1-foot thick, rests on eight coluis above the top of the intake structure. The top surface of the velocity cap is 15-1/2 feet above the ocean bottom and 11-1/2 feet below mean lower low-water.
A 12-foot ID reinforced concrete conduii is connected horizontally to the shoreward side of the intake structure. This conduit is buried beneath the ocean bottom, with a minimum of 4 feet of sand cover over its top and 4 feet of rock cover surrounding the intake structure.
All sand cover was placed so as to approximate the local ocean bottom profile.
Water entering the top of the intake structure is accelerated to a design velocity of about 2.5 feet per second and directed into a 12-foot ID reinforced concrete conduit.
As the water enters the concrete conduit from the structure, it is accelerated to a design velocity of 6.9 feet per second. The circulating water system is designed to deliver 350,000 gpm at this velocity.
The offshore system joins the onshore portion of the circulating water system at the screenwell. The screenwell is located just inside the seawall on the Station property.
Cooling water entering the onshore system passes, through a coarse bar screen, through finer traveling screens, and proceeds to two circulating water pumps designed to operate at 175,000 gpm.
Water entering the screenwell structure is decelerated so that the approach velocity at the screens is approximately 2.0 feet per-second.
The circulating water system uses three methods of handling the marine growth and debris associated with the flow of seawater through the plant condensers. These are heat treating, bar and traveling screens, and chlorination.
Heat treatment is used for incrustation control. This method consists of raising the temperature of the condenser inlet water to 105*F which results in a condenser discharge temperature of approximately 125*F and maintaining this temperature for approximately two hours in each conduit once every five to six weeks and occasionally once every four weeks.
This is accomplished by recirculating a portion of the condenser discharge back through the condenser, thereby reducing the cooling water discharge by about 70 percent. Cross-connections between intake and outfall conduits are provided to create the reversal of flow necessary for the treatment of both conduits. The sudden temperature increase of the cooling water causes incrustations growing in the circulating water system to expire, relax their hold, and be flushed out of.the system.
5-16 Amendment No. 76
Traveling and bar screens are provided to remove marine growth and debris from the seawater passing through the screenwell.
The materials removed from the seawater are marine growth, shells, fish, driftwood, and other debris present in the ocean.
For chlorination, sufficient sodium hypochlorite is injected into the circulating water upstream of the circulating water pumps three times condenser internal surfaces.
The traveling screens and bar screens are placed in series, perpendicular to the flow.
The screens are cleaned automatically, with the frequency of cleaning being dependent on the rate of material buildup on the screens.
The bar screens are cleaned by a traveling mechanical rake that deposits accumulated debris, by means of a seawater jet spray washing process, into sluiceways for removal.
The traveling screens are motor driven, and are capable of rotating as a unit in continuous sequence when activated by pressure differential due to trash buildup.
The debris picked up by the traveling screens is also deposited in a sluiceway by means of a seawater jet spray.
5.8.2 Discharge System Under normal operating conditions, the heated cooling water leaves the condenser and is discharged to the ocean through a 12-ft ID 2,600-ft long concrete conduit.
A single point discharge is effected through a discharge structure located in 24 feet of water.
The dimension of the structure is the same as the intake however there is no velocity cap.
The top of the discharge structure is about 11.5 feet below mean lower low-water.
A 12-foot ID reinforced concrete conduit is connected horizontally to the shoreward side of the discharge structure.
This conduit is buried beneath the ocean bottom, with a minimum of 4 feet of sand cover over its top and 4 feet of rock cover surrounding the discharge structure.
All sand and rock cover was placed so as to approximate the local ocean bottom profile.
The water travels through the discharge conduit with a design velocity of 6.9 feet per second and exists with a vertical velocity of about 2.5 feet per second. The vertical orientation creates a single orifice jet diffuser which entrains surrounding cooler water and assists in
-rapid diminution of the discharge temperature.
About seven minutes is required for water to travel from the condensers to the end of the discharge.
5.8.3 (Deleted) 5-17 Amendment No.
TABLE 5.8-1 MAXIMUM DESIGN CONCENTRATIONS OF CHEMICALS AND ELEMENTS ADDED BY THE STATION TO THE COOLING WATER DISCHARGE DURING NORMAL OPERATIONS (DD CLD CD C+
(Deleted) 5 - 2Q Amendment No. 76