Text

Requests Amend to App a of License DPR-67 Adding Requirements for Liquid & Gaseous Effluent Instrumentation & Calibr.No Unreviewed Safety Questions Are Involved
	ML17266A041
Person / Time
Site:	Saint Lucie
Issue date:	03/15/1979
From:	Robert E. Uhrig; FLORIDA POWER & LIGHT CO.
To:	Stello V; Office of Nuclear Reactor Regulation
References
	L-79-61, NUDOCS 7903190246
	Download: ML17266A041 (101)
	v • d • e

P.O. BOX 013100, IvIIAMI, FL 33101 I

FLORIDA POIVER & LIGHT COMPANY March 15, 1979 L-79-61 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Stello:

Re: St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility Operating License DPR-67. A description of the proposed changes, followed by the revised Technical Specification

.pages, is attached.

The proposed amendment has been reviewed by the St. Lucie Facility Review

-Group and the Florida Power 5 Light Company Nuclear Review Board. They have concluded that it does not involve an unreviewed safety question.

Part of the material being proposed for inclusion in the Technical Specifications (Appendix A) is presently in the Environmental Technical Specifications (Appendix B). A proposed amendment to remove this material from the Environmental Technical Specifications is being prepared and will be forwarded to your office within a few weeks. We request that the two proposals be reviewed concurrently.

This amendment is considered a Class III amendment per 10 CFR 170.22.

Accordingly, a check for four thousand dollars ($ 4,000.00) is enclosed.

Very tr 1 . yours, obert E. Uhrig Vice President Advanced Systems 8 Technology

~

REU:MAS:cf Attachment 9-".cf>ei,. 5'o~D ~

C~r'rol~'f o5I'Fmg&

cc: Mr. James P. O'Reilly, Region II ~.'-' '5'Z2 etBmi!m aR ~ g'i ~P Mr. R. W. Zavadoski, Region II R"MLMC7tBC~i'IG f:iEE Harold F. Reis, Esquire 79 O S X 9 O S 94 PEOPLE... SERVING PEOPLE

C CHANGE INDEX

. Page 1 Pa e 8 Revised or New Descri tion 1-6 Revised Page Defines Gas Radwaste Added 1.30 System 1-8 Revised Defines new effluent Added 4/M & P Frequencies frequencies 3/4 3-30 Revised Revise to permit discharge of gas decay tank after loss 3/4 3-31 of 1 channel 3/4 3-32 3/4 3-41 New Page Add requirements for liquid 3/4 3-42 New Page effluent instrumentation and 3/4 3-43 New Page calibration 3/4 3-44 New Page 3/4 3-45 New Page 3/4 3-46 New Page 3/4 3-47 New Page Add requirements for-gaseous 3/4 3-48 New Page effluent instrumentation and 3/4 3-49 New Page calibration 3/4 3>>50 New Page 3/4 3-51 New Page 3/4 3-52 New Page 3/4 3-53 New Page E

3/4 11-1 New Page Add requirements for liquid 3/4 11-2 New Page effluent concentration, dose, 3/4 11-3 New Page sampling frequencies and waste 3/4 11-4 New Page (Map) treatment operation 3/4 11-5 New Page 3/4 11-6 New Page 3/4 11-7 New Page Add requirements for gaseous 3/4 11-8 New Page effluent dose, sample frequencies, 3/4 11-9 New Page and waste treatment system 3/4 11-10 New Page operations 3/4 11-11 New Page 3/4 11-12 New Page 3/4 11-13 New Page Add 40 CFR 190 requirement 3/4 11-14 New Page Add requirement for limiting storage tank contents 3/4 12-1 New Page Add requirements for the radio-3/4 12-2 New Page logical environmental monitoring 3/4 12-3 New Page program 3/4 12-4 New Page 3/4 12-5 New Page 3/4 12-6 New Page 3/4 12-7 New Page

CHANGE INDEX Page 2 Pa e 8 Revised or New Descri tion 3/4 12-8 New Page Add requirements for the Radio-3/4 12-9 New Page logical Environmental Honitoring 3/4 12-10 New Page Program 3/4 12-11 New Page B-3/4 3-4 New Page Bases B-3/4 11-1 New Page Bases B-3/4 11-2 New Page B-3/4 11-3 New Page B-3/4 11-4 New Page B-3/4 U.-5 New Pa e B-3/4 12-1 New Page Bases 6-7 Revised Page Add FRG review to Radiological Environmental Monitoring Program 6-13 Revised Page Add g and h to 6.8.1 for required procedures 6-14 Revised Page 6.8.2 moved from page 6-13 to page 6-14 and 6.9.1.3 moved off of page 6-14 6-15 Revised Item 6.9.1.3 moved to top of 6-15 from 6-14 Old 6-16 Now Page 6-19 See 6-19 below Old 6-17 Now Page 6-20 See 6-20 below Old 6-18 Now Page 6-21 See 6-21 below New 6-16 New Annual Radiological Environ-mental Op. Report New 6-17 New Table 6.9-1 New 6-18 New Semi-annual Effluent Report 6-19 Revised Formerly Page 6-16 6.9.1.6 now 6.9.1.10 6.9.1.7 now 6.9.1.11 6.9.1.8 now 6.9.1.12

f CHANGE INDEX Page 3 Revised or New Descri tion Revised Formerly Page 6-17.

Item j added after i on new 6.9.1.12 prompt noti-fication (Old 6.9.1.9 off page)

Revised Formerly Page 6-18.

6.9.1.9 now 6.9.1.13 for 30 day written report.

Item 'e added after new 6.1.1.13 d.

Revised Item k added to 6.9.2.

Item 1 added to 6.9.2 Special Reports.

New Table 6.9-2 Revised Old Page 86-19 Old 6.10.2 Item C was "Records of facility radiation and con-tamination surveys". This has been deleted. New Item C was formerly Item K.

Revised Old Page 6-20.

Deleted 6.10.2 Item K 6.12, 6.12.1 a., and 6.12.1 b.

are reworded.

added.

Revised and New Item 6.12.1.C was added.

6.12.2 was added.

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.27 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel s'ensor until the ESF equipment is capable of performing its safety 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.

PHYSICS TESTS 1.28 PHYSICS TESTS shall be those tests performed to measure the funda-mental nuclear characteristics of the reactor core and related instrumenta-tion and 1) described in Chapter 14.0 of the FSAR, 2) authorized under the provisions of 10 CFR 50.59, or 3) otherwise approved by the Commission.

UNRODDED INTEGRATED RADIAL PEAKING FACTOR Fr 1.29 The UNRODDED INTEGRATED RADIAL PEAKING FACTOR is the ratio of the peak pin power to the average pin power in an unrodded core, excluding tilt.

GASEOUS RADWASTE TREATMENT SYSTEM 1.30 A GASEOUS RADNASTE TREA&IENT SYSTEM is any system designed and in-stalled to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system.

ST. LUCIE UNIT 1 1-6 3/15/79

TABLE 1.2 PRE UENCY NOTATION NOTATION At least once per 12 hours At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months At least once per 7 days 4/M* At least 4 per month and a minimum of 48 per year At least once per 31 days At least once per 92 days SA At least once per 6 months At least once per 18 months S/U Prior to each reactor start up Completed prior to each release N.A. Not Applicable

Por Radioactive Effluent Sampling.

- Por Radioactive Batch Releases only.

ST. LUCIE UNIT 1 1-8 3/15/79

INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LQ1ITING CONDITION FOR OPERATION 3.3.3.4 The meterological monitoring instrumentation channels shall be operable as per Table 3.3-8.

APPLICABILITY: At all times ACTION:

a) With the number of OPERABLE meteorological monitoring channels less than required by Table 3.3-8, the Licensee should suspend all release of gaseous radioactive material from the radwaste gas decay tanks until the inoperable channel(s) is restored to OPERABLE status.

b) With less than the Minimum Channels OPERABLE as specified by Table 3.3-8, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status.

c) The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.4 One WIND SPEED, ONE WIND DIRECTION, and TWO AIR TEMPERATURE INSTRUMENTATION CHANNEL(S) shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALI-BRATION operations at the frequencies shown in Table 4.3-5.

3/4 3-30 3/J5/79 ST LUCIE UNIT 1

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION INSTRUMENT .MINIMUM INSTRUMENT & ELEVATION MINIMIM CHANNELS ACCURACY OPERABLE

1. WINDSPEED Nominal Elev (10 meters) + 0.5 *mph 1A a) b) Nominal Elev (57.9 meters) + 0.5 *mph N.A.

2. WIND DIRECTION Nominal"'Elev (10 meters) + 1B a) 5 b) Nominal Elev (57.9 meters + 5 N.A.

3. AIR T~ERATURE (Delta T) 1C a) Nominal Elev (10 meters) i0,10C**

+O.loC** 1C b) Nominal Elev (57.9 meters) c) Nominal Elev (33.5 meters) +0, loC** N.A.

+ Starting speed of anemometer shall be ( 1 mph

- hT measurement channels only A The 57.9 meter Channel may be substituted for the 10 meter wind speed for up to 30 days in. the event the 10 meter Channel is INOPERABLE. Wind Speed Data from the 57.9 meter elevation should be adjusted using the wind speed power law:

S 10 meters =(/s 57.9 meters (0.1727) where:

S wind speed in mph n = 0.25 for Pasquill Vertical Stability Classes A,B,C,D.

n = 0.50 for Pasquill Vertical Stability Classes E,F,G.

1.727 x 10 1 = constant = 10 meters/57.9 meters B The 57.9 meter Channel may be substituted for the 10 meter Wind Direction Channel for up to 30 days in the event the 10 meter Channel is INOPERABLE.

C The 33.5 meter Channel may be substituted for one of the 10 meter or 57.9 meter Temperature Channels for up to 30 days if one of the Channels is INOPERABLE. The data should always be normalized to C/100 meters to determine the vertical stability class.

3/15/79 ST LUCIE UNIT 1 3/4

TABLE 4.3-5 METEOROLOGICAL MONITORING. INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL C1 CANNEL CA INSTRUMENT CHECK CALIBRATION C'

n l. HIND SPEED H a) Nominal Elev (10 meters) D SA b) Nominal Kiev (57.9 meters) D* SA*

2. HIND DIRECTION a) Nominal Elev (10 meters) D SA b) Nominal Elev (57.9 meters) D* SA*

3. AIR TEMPERATURE (Delta T) a) Nominal Elev (10 meters) D SA b) Nominal Elev (57.9 meters) D SA c) Nominal Elev (33.5 meters) D* SA~

Required only if these Channels are being substituted for one of the Minimum Channels Operable as per Table 3.3-8.

e INSTRUMENTATION RADIOACTIVE LI UID EFFLUENT INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.8 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their alarm/trip setpoints set to .ensure that the limits of Specification 3.11.1.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-11.

ACTION:

a. With a radioac'tive liquid effluent monitoring instrumentation

'ill channel alarm/trip setpoint less conservative than a value which ensure that the limits of 3.11.1.1 are met, immediately suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable.

b. With less than the number of channels required OPERABLE by Table .

3.3-11, take the ACTION shown in Table 3.3-11.

c.'he provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIR&KNTS 4.3.3.8.1 The setpoints shall be determined by using the methodology described in the in-plant procedures and shall be posted in the Reactor Control Room.

4.3.3.8.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, AND CHANNEL FUNCTIONAL TEST operations during the Modes and at the frequencies shown in Table 4.3-11.

3/4 3-41 ST. LUCIE UNIT 1

TABLE 3.3-11 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION INSTRUMENT MINIMUM CHANNELS OPERABLE APPLICABILITY ACTION

1. Gross Radioactivity monitors, providing automatic termination of release

a. Liquid radwaste effluent line At all times* 18

b. Steam Generator Blowdown effluent line At all times* 19

2. Gross Radioactivity Monitors not providing automatic termination of release

a. Component cooling water system At all times* 20

During releases via this pathway

TABLE 3.3-11 (Continued)

TABLE NOTATION ACTION 18 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may be resumed for up to 14 days, provided that prior to initiating a release:

l. At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3 and;

2. 't least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 19 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue indefinitely if there is no primary-to-secondary leakage indicated by the air ejector monitor. If the air ejector monitor indicates primary-to-secondary leakage, releases may continue for up to 14 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at limit of detection of at least 10 7 pCi/gram:

1. At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is >0.01 pCi/gram DOSE EQUIVALENT I-131.

2. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the specific activity of the secondary coolant is <0.01 llCi/gram DOSE EQUIVALENT I-131.

ACTION 20 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for'p to 14 days provided that at least once per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months grab samples are collected and analyzed for gross radio-activity (beta or gamma) at a .limit of detection of at least 10 "pCi/ml.,

ST. LUCIE UNIT 1 3/4 3-43 3/15/79

TABLE 4.3-11 RADIOACTIVE LI UID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS I

CHANNEL CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION FUNCTIONAL TEST

1. Gross Beta or Gamma Radioactivity Monitors providing alarm and automatic isolation Liquid Radwaste Effluent Line R(3) e(i)

b. Steam Generator Blowdown Effluent Line R(3) e(i)

2. Gross Beta or Gamma Radioactivity Monitors providing alarm but not providing automatic isolation (4)

a. Component Cooling Water Sys. R(3) e(2)

During releases via this pathway

TABLE 4.3-11 (Cont'd)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(2) The CKQTNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(3) The initial CHANNEL CALIBRATION for radioactivity measurement in-strumentation shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been calibrated against standards certified by the NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per eighteen months. This can normally be accomplished during refueling outages. (Existing plants may substitute previously established calibration procedures for this requirement.)

,ST: LUCIE UNIT 1 3/4 3-45 3/15/79

TABLE 4.3-11 (Cont'd)

(4) This requirement is applicable only to systems where the service water system or component cooling water system is discharged to an effluent stream.

ST. LUCIE UNIT 1 3/4 3-46 3/15/79

INSTRKKNTATION RADIOACTIVE GASEOUS PROCESS AND EFFLUENT MONITORING INSTRRKNTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous process and effluent monitoring instru-mentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of 3.11.2.1 are met, declare the channel inoperable.

b. With less than the number of channels required OPERABLE by Table 3.3-12, take the ACTION shown in Table 3.3-12.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.3.3.9.1 The setpoints shall be determined by using the methodology described in the in-plant procedures and shall be posted in the Reactor Control Room.

4.3.3.9.2 Each radioactive gaseous process or effluent monitoring instru-mentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-12.

ST. LUCIE - UNIT 1 3/4 3-47 3/15/79

TABLE 3.3-12 RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRRKNTATION I

g MINIMUM CUANNELS INSTRRKNT OPERABLE APPLICABILITY PARAMETER ACTION

l. Haste Gas Holdup System

a. Noble Gas Activity Monitor Radioactivity Rate 25 Measurement

2. Plant Vent

a. Noble Gas Activity Monitor Radioactivity Rate Measure- 27 ment

b. Iodine Sampler Cartridge Verify Presence of Cartridge 30

c. Particulate Sampler Filter Verify Presence of Filter 30

During releases via this pathway

TABLE 3.3-1 (Cont'd) n I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRlBKNTATION

? MINIMUM CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAHETER ACTION

3. Fuel Building Vent

a. Noble Gas Activity Monitor Radioactivity Rate Measure- 27 ment

b. Iodine Sampler Cartridge Verify presence of cartridge 30

c. Particulate-Sampler Filter Verify presence of filter 30

4. Blowdown Building,Vent System

a. Noble Gas Activity Monitor Radioactivity Rate Measure- 27 ment

b. Iodine Sampler Cartridge Verify presence of cartridge 30

c. Particulate Sampler Filter Verify presence of filter 30

5. Air Ejector Vent

a. Noble Gas Activity Monitor '1) Radioactivity Rate Measure-ment 28 CJl U3

During releases via this pathway

TABLE 3.3-12 (Cont'd)

TABLE NOTATION ACTION 25 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank may be released to the environment for up to 14 days provided that prior to initiating the release:

l. At least two independent samples of the tank's contents are analyzed, and

2. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineup; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 28 days provided grab samples are collected and analyzed for gross activity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 28 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately route the Air Ejector Vent to the Plant Vent Pathway.

ACTION 30 With the number of channels OPERABLE less than required:by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue indefinitely, provided samples are continuously collected with auxiliary sampling equipment for periods on the order of seven (7) days and analyzed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of the end of sample collection.

ST. LUCIE UNIT 1 3/4 3-50 WiSI79

TABLE 4.

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION FUNCTIONAL TEST

1. l0aste Gas Holdup System

a. Noble Gas Activity Monitor R(3) e(l)

2. Plant Vent

a. Noble Gas Activity Monitor R(3) q(2)

b. Iodine Sampler N.A. N.A.

c. Particulate Sampler N.A. N.A.

3. Fuel Building Vent

a. Noble Gas Activity Monitor R(3) O(2)

b. Iodine Sampler D* N.A. N.A.

c.'articulate Sampler N.A. N.A.

During releases via this pathway

TAB .3-12 (Cont'd)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRRfENTATION SURVEILLANCE RE UIREMENTS CHANNEL CHANNEL CHANNEL INSTRUMENT CHECK .CALIBRATION FUNCTIONAL TEST

4. Blowdown Building Vent System

a. Noble Gas Activity Monitor D* R(3) O(2)

b. Iodine Sampler DA N.A. N.A.

c. Particulate Sampler N.A. N.A.

5. Air Ejector Vent

a. Noble Gas Activity Monitor R(3) e(2)

During releases via this pathway

TABLE 4.3-12 (Cont'd)

TABLE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exist:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

l. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure.

3. Instrument controls not set in operate mode.

(3) The initial,.CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more of the reference standards traceable to the National Bureau of Standards or using standards that have been calibrated against standards certified by the NBS. These standards should permit calibrating the system over its intended range of energy and rate capabilities. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used, at intervals of at least once per eighteen months.

This can normally be accomplished during refueling outages. (Existing plants may substitute previously established calibration procedures for this requirement.)

ST. LUCIE UNIT 1 3/4 3-53 3/15/79

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LI UID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The once diluted concentration of radioactive material released from the site to unrestricted areas (see Figure 3.11-1) shall be limited to the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. The once diluted concentration for total dissolved or entrained noble gases shall be limited to 2 X 10 4 pCi/ml.

APPLICABILITY: At all times.

ACTION:

With the concentration of radioactive material released from the site to un-restricted areas exceeding the above, limits, immediately restore concentration wi'thin the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.

SURVEILLANCE RE UIREMENTS 4.11.1.1.1 The instantaneous concentration of radioactive material in liquid effluents released from the site shall be monitored in accordance with Table 3 ~ 3 11 ~

4.11.1.1.2 The liquid effluent continuous monitors having provisions for automatic termination of liquid releases, as listed in Table 3.3-11, shall be used to limit the concentration of radioactive material released at any-time from the site to unrestricted areas to the values given in Specification 3.11.1.1.

4.11.1.1.3 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1. The results of pre-release analyses shall be used with the calculational methods in the in-plant. procedures to assure that the concentration at the point. of release is limited to the.,values in Specification 3.11.1.1.

4.11.1.1.4 The results of the post release calculations shall be performed using calculational methods in the in-plant procedures to.assure that the concentra-tions at the point of release are limited to the values in Specification 3.11.1.1.

4.11.1.1.5 The radioactivity concentration of liquids discharged from continuous r'elease points shall be determined by collection and analysis of samples in accordance with Table 4.11-1. The results of the analyses shall be used with the calculational methods in the in-plant procedures to assure that the concentra-tions at the point of release are limited to the values in Specification 3.11.1.1.

ST. LUCIE UNIT 1 3/4 11-1 3/15/79

TABLE 4.11-1 RADIOACTIVE LI UID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Sampling Analysis Type of Detection (LLD)

Liquid Release Type Frequency Frequency Activity Analysis (pCi/ml) a,b A. Batch Haste Principal Gamma Release Tanksc Emitters 5 X 10 Each Batch Each Batch I-131 1 X 10-6 p Dissolved and One Batch/M Entrained Gases 1 X 10 H-3 1 X 10 Gross Alpha 1 X 10 Each Batch Compositee Sr-89, Sr-90 5 X 10 8 Each Batch Compositee B. Plant Continuous Principal Gamma Releases f,g Emittersd 5" X 10 4/M 4/M I-131 1X106 Dissolved and Entrained Gases 1 X 10 5 1 X 10 4/M M 'ross Alpha 1 X 10 Compositee 4/M Sr-89, Sr-90 5 X 10-8 Compositee ST LUCIE - UNIT 1 3/4 11-2 3/15/79

TABLE 4.11-1 (Continued)

TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.12.1 of Specification 4.12.1.1.

b. For radionuclides identified by gamma spectrum analysis it may not be possible to measure certain radionuclides near their LLD limit when they are in the presence of .other radionuclides at higher concentration. When a radionuclide's calculated LLD is greater than its listed LLD limit, the activity of the radionuclide should be calculated using measured ratios with those radionuclides which are routinely identified and measured.

If a ratio activity cannot be determined, the calculated LLD should be assigned as the activity of the radionuclide.

c. A batch release is the discharge of liquid wastes of a discrete volume.

d. The principal gamma emitters for which the LLD limit specification will apply are exclusively the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Ho-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.

e. A composite sample is one in which the quantity of liquid sampled is pro-portional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

f. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release.

g. If Component Cooling Water activity >1 x 10 pCi/ml, perform a weekly gross activity on the Intake Cooling Water System outlet to ensure the activity level is < a 1 x 10 7 pCi/ml LLD limit. If ICW is >1 x 10 pCi/ml, perform analysis in accordance with a Plant Continuous Release on this Table.

ST LUCIE - UNIT 1 3/4 I

3/15/79

Denotes Unrestricted Area Boundry Line for. the ST. LUCIE SITE jNrPgg)','c y, z 'P:.; P'~jc; "..+ 'yg> r4 0".,~~/~446>~~~.'.~PA>v!+Ay~~."!.:)(~~i->< Minimum Distance for Radioactive Gaseous Releases from Plant Vent to Site Boundry Discharge

. Radioactive Normal Point)-

f+

SCALE IN FEET 0 l000 2000 3000 Figure 3.1 ll-i Qnaestrieted Area Seen@ry For Yhe St. t,ucie Site ST ~ LUCIT - UNIT 1 3/4 11-4 3/15/79

RADIOACTIVE EFFLUENTS DOSE LIHITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 3.11-1) shall be limited:

a. During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ, and APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies'the cause(s) for exceeding the limit(s) and define's the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the remainder of the current calendar quarter. The Special Report exempts a Licensee Event Report on the above limits.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable SURVEILLANCE RE UIRE2KNTS 4.11.1.2.1 Dose Calculations. Cumulative dose contributions from liquid effluents shall be determined in accordance with in-plant procedures at least once per 31 days.

ST. LUCIE UNIT 1 3/4 11-5 3/15/79

I RADIOACTIVE EFFLUENTS LI UID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The appropriate subsystems of the liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid waste prior to their discharge when the projected monthly dose due to liquid effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over 31 days would exceed 0.12 mrem to the total body.

APPLICABILITY: At all times.

ACTION

h. With radioactive liquid waste being discharged without treatment

'and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information (The Special Report exempts a Licensee Event Report on the above limits):

l. Identification of equipment or subsystems not OPERABLE and a description of alternate equipment used for treatment of radioactive liquid effluent.

2. Action(s) taken to restore the inoperable equipment, or backup equipment, to OPERABLE status.

3. Summary description of action(s) taken to prevent a recurrence.

b. 'he provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days.

4.11.1.3.2 The appropriate liquid radwaste subsystems shall be demonstrated OPERABLE at least once per 92 days unless the appropriate liquid radwaste subsystem has been utilized to process radioactive liquid effluents during the previous 92 days.

ST. LUCIE UNIT 1 3/4 11-6 3/15/79

RADIOACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS DOSE RATE LIHITING CONDITION FOR OPERATION 3.11.2.1 The instantaneous dose rate in unrestricted areas (see Figure 3.11-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values:

a. The dose rate limit for noble gases shall be <500 mrem/yr to the total body and <3000 mrem/yr to the skin, and

b. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days shall be <1500 mrem/yr to any organ.

APPLICABILITY: At all times.

ACTION:

With the dose rate(s) exceeding the above limits, immediately decrease the release rate to comply with the limit(s) given in Specification 3.11.2.1 and provide prompt notification to the Commission pursuant to Specification 6.9.1.12.

SURVEILLANCE RE UIRBKNTS 4.11.2.1.1 The instantaneous release rate of noble gases in gaseous effluents shall be continuously monitored for the release points given in Table 3.3-12.

4.11.2.1.2 The release rate of radioactive materials other than noble gases, in gaseous effluents shall be determined by obtaining representative samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2.

4.11.2.1.3 The instantaneous dose rate in unrestricted areas, due to radio-active materials other than noble gases released in gaseous effluents, shall be determined to be within the required limits by using the methodology prescribed by the in-plant procedures on the results of. the sampling and analysis program specified in Table 4.11-2.

'ST. LUCIE UNIT 1 3/4 11-7 3/15/79

TABLE 4.11-2 RADIOACTIVE GASEOUS HAS AlfPLING AND ANALYSIS PROGRAM Sampling Minimum Type of Lower Limit of Gaseous Release Type Frequency Analysis Activity Analysis Detection (OLD)

Frequency (pCi/ml)

A. Was Gas Storage P P Noble Gas Tank (Batch) Each Tank Each Tank Princi al Gamma Emitters 1X104 H-3 d .1X 10 B. Containment Purge P P Noble Gas (Batch) Each Purge Each Purge Princi al Gamma Emitters c 1 X 10 H-3 d 1 X 10 6 C. Plant Vent Noble Gas Fuel Building Vent Princi al Gamma Emitters 1 X 10 Blowdown Bldg.

Vent Systeme H-3 D. All Release Types I-131 1 X 10-12 as listed in Continuous Charcoal C. above Sample I-133 1X10 4/M Continuous Sample

'articulate f Particulate Principal Gamma Emitters 1 X 10 M

Continuous f Composite Gross Alpha 1X10 Particulate Sample Continuous f Composite Sr-89, Sr-90 1 X 10 Particulate Sample

TABLE 4.11-2 (Continued)

TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation a.

of Table 4.12-1 of Specification 4.12.1.1.

b. For radionuclides identified by gamma spectrum analysis it may not be possible to measure certain radionuclides near their LLD Limit when they are in the presence of other radionuclides at higher concentration. When a radionuclide's calculated LLD is greater than its listed LLD Limit, the activity of the radionuclide should be calculated using measured ratios with those radionuclides which are routinely identified and measured. If a ratio activity cannot be determined, the calculated LLD should be assigned as the activity of

.the radionuclide.

c~ The principal gamma emitters for which the LLD Limit Specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for noble gas emissions and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Ho-99, Cs-134, Cs-137, Ce-141, Ce-144, and I-131 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 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.

d. Tritium grab samples shall be taken prior to each batch release, but the sample may be analyzed after the batch release when the sample counting solution has stabilized to allow an accurate determination of activity.

e. Sampling Frequency and Minimum Analysis Frequency are applicable only during releases via this pathway.

f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period'n Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

g. If the analysis frequency is daily, the LLD limit may be increased by a factor of 10.

ST LUCIE UNIT 1 3/4 11-9 3/15/79,

RADIOACTIVE EFFLUENTS DOSE NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (see Figure 3.11-1) due to noble gases released in gaseous effluents shall be limited to the following:

a. During any calendar quarter, to < 5 mrad for gamma radiation and < 10 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit(s) and define the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter.; The Special Report exempts a Licensee Event Report on the above limits.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.2.1 Dose Calculations - Cumulative dose contributions for the total time period shall be determined in accordance with the methodology in the in-plant procedures at least once every 31 days.

ST. LUCIE UNIT 1 3/4 11-10 3/15/79

RADIOACTIVE EFFLUENTS DOSE RADIOIODINES RADIOACTIVE MATERIAL IN PARTICULATE FORM AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (see Figure 3.11-1) shall be limited to the following:

a. During any calendar quarter to < 7.5 mrem to the total body or any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioiodines, radio-active materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter. The Special Report exempts a Licensee Event Report on the above limits.

b.. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.11.2.3.1 Dose Calculations Cumulative dose contributions for the total time period shall be determined in accordance with the methodology in the in-plant procedures at least once every 31 days.

ST. LUCIE UNIT 1 3/4 ll-ll 3/15/79

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT L'IMITING CONDITION 'FOR OPERATION 3.11.2.4 The appropriate subsystems of the gaseous radwaste treatment system shall be OPERABLE. The gaseous radwaste treatment system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected gaseous effluent doses due to gaseous effluent releases to unrestricted areas (see Figure 3.11-1) when averaged over 31 days would exceed 0.4 mrad for gamma radiation and 0.8 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION:

a. With gaseous waste being discharged for more than 31 days without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which includes the following information (The Special Report exempts a Licensee Event Report on the above limits):

l. Identification of equipment or subsystems not OPERABLE and a description of alternate equipment used for treatment of radio-active gaseous effluents.

2. Action(s) taken to restore the inoperable equipment, or backup equipment, to OPERABLE status.

3. Summary description of action(s) taken to prevent a recurrence.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREHENTS 4.11.2.4.1 Doses due to gaseous releases to unrestricted areas shall be pro-jected at least once per 31 days.

4.11.2.4.2 The appropriate subsystems shall be demonstrated OPERABLE at least once per 92 d'ays unless the appropriate subsystem has been utili ed to process radioactive gaseous effluents during the previous 92 days.

ST. LUCIE UNIT 1 3/4 11-12 3/15/79

RADIOACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.2.5 The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to the total body or any organ (except the thyroid, which is limited to < 75 mrem) over a period of 12 consecutive months.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2.a, 3.11.2.2a, or 3.11.2.3a, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 and limit the subsequent releases such that the dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to < 25 mrem to" the total body or any organ (except thyroid, which is limited to < 75 mrem) over 12 consecutive months. This Special Report shall include an analysis which demonstrates that radiation exposures to all real individuals from all uranium fuel cycle sources (including all effluent pathways and direct radiation) are less than the 40 CFR Part 190 Standard.

Otherwise, obtain a variance from the Commission to permit releases which exceeds the 40 CFR Part 190 Standard. The Special Report exempts a Licensee Event Report on the above limits.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIRE?fENTS 4.11.2.5.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Specifications 3.11.1.2.a, 3.11.2.2.a, and 3.11.2.3.a,'nd in accordance with the in-plant procedure methodology.

4.11.2.5.2 ~Re orts Special Reports shall be submitted as required under Specification 3.11.2.5.a.

ST. LUCIE UNIT 1 3/4 3/15/79

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LDfITING CONDITION FOR OPERATION 3.11.2.7 The quantity of radioactivity contained in each gas storage tank shall be limited to < 285,000 Curies noble gases (considered as Xe-133).

APPLICABILITY: At all times ACTION

a. With the quantity of radioactive material in any gas storage tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.9.1.12.

The written followup report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREKNTS 4.11.2.6 The quantity of radioactive material contained in each gas storage tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

ST. LUCIE UNIT 1 3/4 11-14 3/15/79

3/4. 12 RADIOLOGICAL ENVIRORKNTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. ffith the radiological environmental monitoring program not being conducted as specified in Table 3.12-1, prepare and submit to the Commission, in the Annual Radiological Monitoring Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. (Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavail-ability, or to malfunction of automatic sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period. The sample locations may vary over plant life from the locations given on Table 3.12-1. A current list of sample locations used during the reporting period shall be included in the Annual Radiological Monitoring Report. Sample location changes from the preceding year should be identified along with a brief des-.

cription of the confirmed reason for the change.

b. With the confirmed* level of radioactivity in an environmental sampling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 6.9-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Special Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 6.9-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Monitoring Reports The Special Report exempts a Licensee Event Report.

A confirmatory reanalysis of the o~ri inal~ a duplicate, or a new sample may be desirable, as appropriate. The results of the confirmatory analysis shall be completed at the earliest time consistent with the analysis, but in any case within 30 days.

ST LUCIE UNIT 1 3/4 12-1 3/15/79

r RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING'PROGRAM continued)

LIMITING CONDITION FOR OPERATION

c. With milk or fresh leafy vegetable samples unavailable from any of the sample locations specified by Table 3.12-1, a report shall be included in the Annual Radiological Monitoring Report identify-ing the cause of the unavailability and identifying replacement locations for obtaining samples.

SURVEILLANCE RE UIREMENTS 4.12.1.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 and shall be analyzed pur-suant to the requirements of Tables 3.12-1 and 4.12-1.

ST. LUCIE UNIT 1 3/4 12-2 3/15/79

Table 3.12-1 ST. LUCIE SITE RADIOLOGICAL ENVIROAKNTAL MONITORING PROGRAM nH I

Exposure Pathway Sample Sampling and (b) 'fype and Frequency and/or Sample Locations (a) Collection Frequency of Analysis (b)

l. Airborne

a. Radioiodine 9 locations Continuous operation of Radioiodine canister.

& Particulates H08, H09, Hlo, H12, H14, sampler with collection Analyze at least H30, H32*, H33, & H34 as required by dust loading, weekly( ) for I-131.

but at least weekly( ).

Particulate sampler.

Analyze for gross beta radioactivity > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following filter change.

Perform gamma isotopic analysis on each sample when gross beta activity is > 10 times the yearly mean of the control sample. Perform gamma isotopic analysis on composite (by location) sample at least quarterly (b)

Direct Radiation 9 locations Monthly Gamma dose.

H08, H09, H10, H12, H14, Monthly( )

H30, H32*, H33 and H34

Denotes Control Sample

TABLE 3.12-1 (cont)

ST. LUCIE SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Pathway Sample Sampling and type and Frequency and/or Sample Locations Collection Frequency of Analysis(>)

3 ~ Waterborne

a. Surface 4 Locations Monthly Gamma isotopic and

1) Discharge Canal H36 tritium analysis

2) Ocean H15, H32* Monthly( ).

3) Estuarine H13

b. Ground (well) 2 Locations Quarterly(b) Gamma isotopic and H30, H32* tritium anagysis Quarterly( ~.

c. Drinking 4 Locations Quarterly( ) Gross Beta, gamma isotopic, Hll, H12, H31, H32* and tritium analysis Quarterly(

d. Sediment from 4 Locations Semiannually( ) Gamma lsotop)g analysis shoreline H36 Semiannually

1) Discharge Canal H15, H32*

2) Ocean H13

3) Estuarine

Denotes Control Sample

TABLE 3.12-1 (cont) iST. LUCIE SITE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM C'

Exposure Pathway Sample ~Sampling and (b) type and Frequency W and/or Sample Locations(s) Collection Frequency of Analysis (b)

H I

4. Ingestion 4 Locations Semi-Monthly( Gamma isotopic and I-131 Hol~ H03, H05>> analysis Semi-Monthly(

a. Milk H40*

b. Fish and 2 Locations Semiannually( )- for Gamma isotopic analysis Invertebrates H15, H32* Blue Crab and Fish on edible portions semi-annually (b) .

c. Food Products 6 Locations At harvest time. Gamma isotopic analysis (1) Citrus Hlo, H22, H23, H24, on edible portion. At H26, H39* harvest time.

(2) Leafy 1 Location At harvest time. I-131 analysis. At Vegetation Determined by annual harvest time.

garden census.

5. Land Use Census N.A. N.A. As per 3.12.2

Denotes Control Sample

TABLE 3.12-1 (cont)

TABLE NOTATION (a) Sample locations are shown on Figure 4.12-1.

(b) The following definition of frequencies shall apply to Table 3.12-1 only:

~Weekl - Not less than 48 times per annum-interval may vary by 3 days.

by 7 days.

~Monthl Not less than 10 times per annum interval may vary by 15 days.

~uarterl Not less than 4 times per annum interval may vary by 30 days.

60 days.

12-6 3/15/79 ST. LUCIE-UNIT 1 3/4

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j ~ j O ) ~ o j ~ o a o u o r r 3/15/7g ST. LUG IE UNIT 1 3/4 12-7

TABLE 4. 1 DETECTION CAPABILITIES FOR ENVIRONMENTAL SA1PLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

A ANALYSIS WATER AIRBORN PART- FISH MILK FOOD PRODUCTS SEDIMENT I

(pci/x) TICULATE OR GAS (pCi/Kg, wet) pCi/R (pCi/Kg,- wet) (pCi/Kg, dry)

(pCi/m3)

Gross Beta 4c lxlO-2 2000(1000 )

Mn-$4 15 130 Fe-59 30 260 Co-58, 60 130 Zn-65 30 260 Zr/Nb-95 15e I-131 lc 7 x 10 60d Cs-134, 137 15(10c) ~ 18 lx10 130 15 60 150 Ba/La-140 15e (A

Vl lO

TABLE 4.12-1 (con';t NOTATION a.Acceptable detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

b Table indicates acceptable detection capabilities for radioactive materials in environmental samples. These detection capabilities are tabulated in terms of the lower limits of detection (LLDs). The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely con-cluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 sb LLD = E ' ~ 2.22 ' .

exp(-XAt)

Where LLD is the lower limit of detection as defined above (as pCi per unit mass or volume) ~

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute).

E is the counting efficiency (as counts per disintegration).

V is the sample size (in units of mass or volume).

2.22 is the number of disintegrations per minute per picocurie.

Y is the fractional radiochemical yield (when applicable).

X is the radioactive decay constant for the particular radionuclide.

At is the clasped time between sample collection (or end of the sample collection period) and time of counting.

The value of s b used in the calculation of the LLD for a particular measure-ment system should be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate),

rather than on an unverified theoretically predicated variance. In calculating the LLD for a radionuclide determined by gamma-ray spectrometry, the background should include the typical contributions of other radionuclides normally present in the samples (e.g. potassium-40 in milk samples).

Typical values of E, V, Y and At should be used in the calculation.

c LLD for drinking water d LLD for leafy vegetables e Total for parent and daughter 12-9 3/15/79 ST. LUCIE UNIT 1 3/4

RADIOLOGICAL ENVIRONMENTAL MONITORING'/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the loca-tion of the nearest milk animal, the nearest residence and the nearest garden* of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times.

ACTION:

a~ With a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3.1, pre-pare and submit a report, in the Annual Radiological Environmental Monitoring Report, which identifies the new location(s).

b. With a land use census identifying a location(s) which yields a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, prepare and submit a report, in the Annual Radiological Environmental Monitoring Report, which identifies the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible.

The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program after (October 31) of the year in which this land use census was conducted.

c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1, by door-to-door survey, aerial survey, or by consulting local agriculture authorities.

Broad leaf vegetation sampling may be~erformed at the site boundary in the direction sector with the highest(D7() in lieu of the garden census.

ST LUCIE UNIT 1 3/4 12-10 3/I<5/79

RADIOLOGICAL ENVIROAKNTAL MONITORING 3/4. 12. 3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by NRC.

APPLICABILITY: At all times.

ACTION:

a~ With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Monitoring Report.

b. The provisions of Specification 3.0.3 and 3.0.4 are not applic'able.

SURVEILLANCE RE UIREiENTS 4.12.3 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radio-logical Environmental MonitoriW Report pursuant to Specification 6.9.1.6.

ST.. LUCIE UNIT 1 3/4 12-11 3/15/79

INSTRUMENTATION BASES 3/4.3.3.8 RADIOACTIVE LI UID EFFLUENT INSTRUMENTATION The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm trip setpoints for these instruments shall be calculated in accordance with approved methods in the in-plant procedures to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50.

3/4. 3.3. 9 RADIOACTIVE GASEOUS EFFLUENT INSTRKKNTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with methods in the in-plant procedures to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63 and 64 of Appendix A to 10 CFR Part, 50.

ST. LUCIE UNIT 1 B 3/4 3-4 3/15/79

3/4.11 RADIOACTIVE EFFLUENTS BASES 3/4.11.1 LI UID EFFLUENTS 3/4.11.1.1 CONCENTRATION I

This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table II. This limitation provides addi-tional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within '(1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population.

The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its NPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP)

Publication 2.

3/4.11.1.2 DOSE This specification is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonable achievable",.

Performing the dose calculations in the in-plant procedures implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the in-plant procedures for calculating the doses due to the actual release rates of radioactive materials in liquid effluents

'should be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to. Man from Routine Releases of Reactor Effluents for the purpose of evaluating Compliance with 10 CFR Part 50, Appendix I,"

Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the

~

purpose of. Implementing Appendix I," April 1977.

ST. LUCIE - UNIT 1 B 3/4 11-1 3/15/79

RADIOACTIVE EFFLUENTS BASES This specification applies to the release of liquid effluents from each reactor at the site. For units with shared radwaste treatment systems, the liquid effluents from the shared system are proportioned among the units sharing that system.

3/4.11.1.3 LI UID HASTE TREATMENT The OPERABILITY of appropriate subsystems of the LHT system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provides assur-ance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix A to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suit-able fraction of the guide set forth in Section 11.A of Appendix I, 10 CFR Part 50, for liquid effluents.

3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at any-time at the exclusion area boundary from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table ll. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclusion area boundary, to annual average concentrations exceeding the limits "specified in Appendix B, Table 11 of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for ST. LUCIE UNIT 1 B 3/4 11-2 3/15/79

RADIOACTIVE EFFLUENTS BASES any increase in the atmospheric diffusion factor above that for the ex-clusion area boundary. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to < (500) mrem/year to the total body or to < (3000) mrem/year to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 1500 mrem/year for the nearest cow to the plant.

3/4.11.2.2 DOSE NOBLE GASES This specification is provided to implement the requirements of Sections II.B, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The ACTTON statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."

The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the in-plant procedures for calculating the doses due to the actual release rates of radio-active noble gases in gaseous effluents should be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Han from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "kfethods for Estimating Atmos-pheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Mater-Cooled Reactors," Revision 1, July 1977. The in-plant procedures equations provided for determining the air doses at the.'exclusion area boundary will be based upon the historical (or real) average atmospheric conditions.

3/4.11.2.3 DOSE RADIOIODINES RADIOACTIVE MATERIAL IN PARTICULATE F01Qf AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections II.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting ST. LUCIE UNIT 1 B 3/4 11-3 3/15/79

RADIOACTIVE EFFLUENTS BASES Conditions for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexi-bility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be'ept "as low as is reasonably achievable." The in-plant procedures calculational methods specified in the surveillance requirements implement the requirements in Section III.A of Appendix I that conform-ance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially under-estimated. The in-plant procedures calculational methods for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculating of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Fart 50, Appendix I," Revision I, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Mater-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical (or real) average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate. form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area.

The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and

4) deposition on the ground with subsequent exposure of man.

3/4.11.2.4 GASEOUS HASTE TREATMENT The OPERABILITY of the appropriate subsystems of the gaseous radwaste treatment system ensures that the system will be available for use when-ever gaseous effluents require holdup prior to release to the environment.

The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radio-active materials in gaseous effluents will be kept "as low as is reasonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guide set forth in Sections llB and 11.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

3/15/79 .

ST. LUCIE UNIT 1 B 3/4 11-4

RADIOACTIVE EFFLUENTS BASES 3/4.11.2.5 DOSE This specification is provided to meet the reporting requirements of 40 CFR 190.

3/4.11.2.7 GAS STORAGE TANKS Restricting the quantity of radioactivity contained in each gas storage tank provides assurance that in the event of an uncontrolled release of the tanks contents, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem, as per Safety Guide 24 Rev. 3/23/72 . This is consistent with Standard Review Plan 15.7.1, "Haste Gas System Failure."

3/15/79 ST. LUCIE UNIT 1 B 3/4 11-5

3/4. 12 RADIOLOGICAL ENVIROAKNTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposures of individuals resulting from the station operation. This monitoring program thereby supplements the radio-logical effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Program changes may be initiated based on operational experience.

The detection capabilities required by Table 4.12.-1 are state-of-the-art for routine environmental measurements in industrial laboratories.

The LLD limits for drinking water meet the requirements of 40 CFR 141.

3/4.12.2 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifi-cations to the monitoring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CPR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter. Broad leaf vegetation sampling may be per-fotned at the site bonndaty in the ditection sector with the highest(DTQ) in lieu of performing the garden census.

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.

St.'ucie Unit 1 B 3/4 12-1 3/15/79

ADMINISTRATIVE CONTROLS

e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Manager of Power Resources Nuclear, the Vice President of Power Resources and to the Chairman of the Company Nuclear Review Board.

f. Review of those REPORTABLE OCCURRENCES requires 24 hour notifica-tion to the Commission.

g. Review of facility operations to detect potential safety hazards.

h. Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Company Nuclear Review Board.

i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Chairman of the Company Nuclear Review Board.

Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Company Nuclear Review Board.

k. Review the radiological environmental monitoring program and the results thereof at least once per 12 months.

AUTHORITY 6.5.1.7 The Facility Review Group shall:

a. Recommend to the Plant Manager written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.

b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Vice President of Power Resources and the Company Nuclear Review Board of disagreement between the FRG and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.

ST. LUCIE UNIT 1 6-7 3/15/79

ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The facility shall be placed in at least HOT STANDBY within one hour.

b. The Safety Limit violation shall be reported to the Commission, the Vice President of Power Resources and to the CNRB within '4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; C ~ A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the FRG. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission, the CNRB and the Director of Power Resources within 14 days of the violation.

6.8 PROCEDURES 6.8.1 Hritten procedures shall be established, implemented -and maintained covering the activities referenced below:

a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November, 1972.

b. Refueling operations.

c. Surveillance and test activities of safety related equipment.

d. Security Plan implementation.

e. Emergency Plan implementation.

f. Fire Protection Program implementation.

g. The radiological environmental monitoring program.

h. Offsite releases of gaseous and liquid effluents containing radioactive materials, including effluent monitor setpoints.

ST. LUCIE UNIT 1 6-13 3/15/79

ADMINISTRATIVE CONTROLS 6.8.2 Each procedure and administrative policy of'6.8.1 above, and changes thereto, shall be reviewed by the FRG and approved by the Plant Manager prior to implementation and reviewed periodically as set forth in administrative procedures.

6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:

a. The intent of the original procedure is not altered.

b. The change is approved by two members of the plant management staff, at least one of whom holds a Seni'or Reactor Operator's License on the unit affected.

c.. The change is documented, reviewed by the FRG and approved by the Plant Manager within 14 days of implementation.

6.9 REPORTING RE UIRFMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional. Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by,a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test 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 bh included in this report.

ST. LUCIE UNIT 1 6-14 3/15/79

ADMINISTRATIVE CONTROLS 6.9.1.3 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 the Startup Report does cover all three events (i.e., initial criticality, completion of

'ot startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

ANNUAL REPORT 6.9.1.4 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to triarch 1 of each year. The initial report shall be submitted prior to 1farch 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a~ 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, e.g.,

reactor operations and surveillance, inservice 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 requirements. 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 major work functions.

b. The complete results of steam generator tube inservice inspec-tions performed during the report period (reference Specifica-tion 4.4.5.5.b).

1/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.

2/ This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.

ST. LUCIE UNIT 1 6-15 3/15/79

ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL E~V/IRORKNTAL MONITORING REPORT 3/

6.9.1.6 Routine radiological environmental monitoring reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

6.9;1.7 The annual radiological environmental monitoring reports shall include summaries, interpretations, and a'rend analysis of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental sur-veillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land use censuses required by Specification 3.12.2. If harmful effects are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem.

The annual radiological environmental monitoring reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples 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.

The reports shall also include the following: a summary description of the radiological environmental monitoring program,' map of all sampling locations keyedto a table giving distances'nd direct'ions from one reactor; the result of land use censuses required by the Specification 3.12.2; and tha resn~ts o~rcensee participation 'in the ynterlaboratory Comparison Program required by Specification 3.12.3.

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 6.9.1e8 Routine radioactive effluent release reports covering the operating of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year. The period of the first report shall begin with the data of initial criticality.

3/ A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

3/15/79 ST. LUCIE UNIT 1 6-16

TABLE 6.9-1 FORMAT FOR EWIRONMENTAL RADIOLOGICAL MONITORING PROGRAM

SUMMARY

NAME OF FACILITY ST. LUCIE PLANT UNIT 1 DOCKET NO. 50-335 LOCATION OF FACILITY ST. LUCIE COUNTY FLORIDA REPORTING PERIOD Type and Lower Limit All Indicator Location with Hi hest Annual. Mean Number of Medium or Pathway Tota'umber of Locations Control Locat(ons Nonroutine Sampled of Aaalyses DetectiorP Mean (f) Name Mean (f) Mean (f) Reported (Unit of Measurement) Performed (LLD) Rangeb Distance and Direction Range" Range Measurements Nominal Lower Limit of Detection (LLD) as defined in HASL-300 (Rev. 8/74) pp. D-08-01, 02, 03 at the 95X confidence level.

Mean and range based upon detection measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (f).

ADMINISTRATIVE CONTROLS 6.9.1.9 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 Rev. 1, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof.

The radioactive effluent release reports shall include the following information for all unplanned offsite releases of radioactive materials in gaseous and liquid effluents:

a. A description of the event and equipment involved.

b. Cause(s) for the unplanned release.

c. Actions taken to prevent recurrence.

d. Consequences of the unplanned'elease.

The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calendar quarter as outlined in the in-plant procedures. The assessment of radiation doses shall be performed in accordance with methodology in the in-plant procedures.

ST. LUCIE UNIT 1 6-18 3/15/79

I P ADMINISTRATIVE CONTROLS IfONTHLY OPERATING REPORT 6.9.1.10 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Manage-ment and Program Analysis, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, with a copy to the Regional Office, no later than the 15th of each month following the calendar month covered by the report.

REPORTABLE OCCURRENCES I"

6.9.1.11 The REPORTABLE OCCURRENCE of Specifications 6.9.1.12 and 6.9.1.13 below, including corrective actions and measures to prevent recurrence, shall be reported to the NRC. Supplemental reports may be required to fully describe final resolution of occurrence. In case of corrected or supplemental reports, a licensee event report shall be completed and reference shall be made to the original report date.

PROMPT NOTIFICATION WITH t&ITTEN FOLLOWJP 6.9.1.12 The types of events listed below shall be reported within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of the Regional Office, or his designate no later than the first working day following the event, with a written followup report within 14 days. The written followup report shall include, as a minimum, a completed copy of a licensee event report form. Infor-mation provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a~ Failure of the reactor protection system or other systems subject to limiting safety system settings to initiate the required protective function by the time a monitored para-meter reaches the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.

b. Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the technical specifications.

C~ Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment.

ST. LUCIE UNIT 1 6-19 3/15/79

ADHINISTRATIVE CONTROLS

d. Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a SHUTDOHN HARGIN less conservative than specified in the technical specifica-tions; short-term reactivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality.

e. Failure or malfunction of one or more components which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the FSAR.

f. Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to cope with accidents analyzed in the FSAR.

ge Conditions arising from natural or man-made events that, as a direct result of the event require unit shutdown, operation of safety systems, or other protective measures required by technical specifications.

h. Errors discovered in the transient or accident analyses or in the methods used for such analyses as described in the safety analysis report or in the bases for the technical specifica-tions that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.

Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifica-tions bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or cor-rective measures to prevent the existence or development of an unsafe condition.

Occurrence of radioactive material contained gaseous holdup tanks in excess of that permitted by the limiting condition for operation established in the technical specifications.

ST. LUCIE UNIT 1 6-20 3/15/79

P ADMINISTRATIVE CONTROLS THIRTY DAY WRITTEN REPORTS 6.9.1.13 The types of events listed below shall be the subject of written reports to the Director of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form. Information provided on the licensee event report form shall be supplemented, as needed, by additional narrative material to provide complete explanation of the circumstances surrounding the event.

a0 Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those esgablished by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.

b. Conditions leading to operation in a degraded mode permitted by a limiting condition for operation or plant shutdown re-quired by a limiting condition for operation.

C~ Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems'.

d~ Abnormal degradation of systems other than those specified in 6.9.1.12.c above designed to contain radioactive material resulting from the fission process.

e, An unplanned offsite release of 1) more than 1 curie of radioactive material in liquid effluents, 2) more than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactiv'e material shall include the following information:

l.. A description of the event and equipment involved.

2. Cause(s) for the unplanned release.

3. Actions taken to prevent recurrence.

4. Consequences of the unplanned release.

ST. LUCIE UNIT 1 6-21 3/15/79

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be sub-mitted covering the activities identified below pursuant to the requirements of the applicable reference specification:

a. Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3 ~

b. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.

c. Inservice Inspection Program Reviews, Specifications 4.4.10.1 and 4.4.10.2.

d. ECCS Actuation, Specifications 3.5.2 and 3.5.3.

e. Sealed Source leakage in excess of limits, Specification 4.7.9.1.3.

Seismic event analysis, Specification 4.3.3.3.2.

g. Beach survey results, Specification 4.7.6.1.1.

h. Core Barrel Movement, Specifications 3.4.11 and 4.4.11.

i. Fire Detection Instrumentation, Specification 3.3.3.7.

Fire Suppression Systems, Specification 3.7.11.1.

k. Exceeding one or more LCO's for Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4, or 3.11.2.5 involving radiation dose from radioactive effluents.

1. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 6.9-2 when averaged over any calendar quarter sampling period. When more than one of the radionuclides in Table 6.9-2 are detected in the sampling medium, this report shall be submitted if:

concentration 1) concentration (2) limit level (1) limit level (2)

When radionuclides other than those in Table 6.9-2 are detected and are the result of plant effluents, this report shall be submitted if the quarterly dose to an individual is equal to or greater than the quarterly limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; how-ever, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Monitoring Report.

6-22 3/15/79 ST. LUCIE UNIT 1

TABLE t NONROUTINE REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES nH I

Broad Leaf Water Airborne Particulate Fish Milk Vegetation Analysis (pci/1) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/1) (pCi/Kg, wet)

H-3 2X10 Mn-54 1 X 10 3 X 10 Fe-59 4 X 10 1 X 10 Co-58 1 X 10 3 X 104 Co-60 3 X 10 1 X 104 Zn-65 3 X 10 2X10 Zr-Nb-95 4 X 10 I-131 0.9 1 X 10 Cs-134 30 10 1 X 10 60 1 X 103.

Cs-137 50 20 2 X 10 70 2 X 10 2(l)

GO Ba-La-140 2 X 10 3 X 10 Vl

'LD (1) Total for parent and daughter.

ADMINISTRATIVE CONTROLS 6.-10 RECORD RETENTION 6.10.1 The following records shall be retained for at least five years:

a. Records and logs of facility operation covering time interval at each power level.

b. Records and logs of principal maintenance activities, inspec-tions, repair and replacement of principal items of equipment related to nuclear safety.

c. All REPORTABLE OCCURRENCES submitted to the Commission.

d. Records of surveillance activities, inspections and calibrations required by these Technical Specifications;

e. Records of reactor tests and experiments.

f. Records of changes made to Operating Procedures.

g. Records of radioactive shipments.

h. Records of sealed source leak tests and results.

Records of annual physical inventory of all sealed source material of record.

6.10.2 The following records shall be retained for the duration of the Facility Operating License:

a~ Records and drawing changes reflecting facility design modifi-cations made to systems and equipment described in the Final Safety Analysis Report.

b. Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.

C~ Records of meetings of the FRG and the CNRB.

d. Records of radiation exposure for all individuals entering radiation control areas.

ST. LUCIE UNIT 1 6-24 3/15/79

ADMINISTRATIVE CONTROLS

e. Records of gaseous and liquid radioactive material released to the environs.

f. Records of transient or operational cycles for those facility components identified in Table 5.9-1.

g. Records of training and qualification for current members of

'the plant staff.

h. Records of in-service inspections performed pursuant to these Technical Specifications.

Records of Quality Assurance activities required by the QA Manual.

Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.

6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

6.12 HIGH RADIATION AREA OPTIONAL) 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c) (2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*.

Any individual or group. of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset inte-grated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made know-ledgeable of them.

Health Physics personnel shall be exempt from the RWP issuance require-ment during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.

ST. LUCIE UNIT 1 6-25 3/] 5/79

I" ADMINISTRATIVE CONTROLS C~ An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.

This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.

6.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr. In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the 'Shift Supervisor on duty and/or the Plant Health Physicist.

ST LUCIE UNIT 1 6-26 3/15/79

(e ~ u ~'

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR!7903190246 DOC ~ DATE! 79/03/15 NOTARIZED> YES DOCKET ¹ FACILo50~335 ST ~ LUCIE> PLANTg UNIT ig FLORIDA PONER 5,LIGHT CO ~,

05000335.

AUTH;NAME'UTHOR AFFILIATION UHRIGt'R ~ E FLORIDA'OWER 8 L'IGHT CO ~

REC IP NAME

~ RECIPIENT AFF IlIATION STELLOeV ~ DIVISION OFl OPERATING REACTORS

SUBJECT:

REQUESTS AMEND TO 'APP- A OF LICENSE'PR 67 ADDING REQUIREMENTS 'OR LIQUID 8 GASEOUS EFFLUENT, INSTRUMENTAT~ION 8 GAL I BR ', NO 'UNRE VIEWED- SA TY, QUESTIONS. ARE I'NVOLVED~

DISTRIBUTION CODE$ A009S "CO KS RECEIVED!LTR ~>~ ENCL'Q '.SIZE!

l I DISTRIBUTION AFTER ISSUANCE'F OLI

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RECIPIENT COPIES RECIPIENT 'COPIES ID CODE/NAME LTTR'NCL" 'ID CODE/NAME; LTTR ENCL)

ACTION~ 05 BC o 7. 7

INTERNAL'1 1 1 02 NRC PDR 1 1 12 2" 10 PLANT SYS BR 1 15 EEB 1. 1 16 AD SITE TECH 1 1 17 HYDRO~MTR BR 1 1 18 MARKKK, 1 1 19 EFFLi TRT SYS 2 2 21 RAD ASMT BR 1 1 22 NAGNERgP ~ ; 1 DIRECTOR DSE~ 0 OELD 1" 0 TA/EDO 1 0 6~ inlKNAn> (

EXTERNALS 03 LPDR 1 1 00 NSIC 23 ACRS 16 16 wa 21879 TOTAL NUMBER OF.'OPIES REQUIRED LTTR 41 ENCL'. )3e.

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44
STATE OF FLORXDA )
COUixlTY OF DADE
.) ss 3
E. A. Adomat
, being first duly sworn, deposes and says:
Thai he is Executive Vic PY. ~
of Florida Power a Light Comp ny, tile licensee herein; k That he has executed the foregoing document;'hat the state- =-
ments made in this said document are true and correct to the best of .his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said, Licensee-E. A. Adomat Subscr'ibed and sworn to before. me this
@ay a+ 19 ~9 NOTARY PUBLIC, n and for the County of Dade, State of Flori NOTA' r%5UC STATE OP ~ORIDA st VOCE AY COMMiSSlOtt EXPiREG t.IARCtl 27, 1582 jiffy commission expires: RDNDED THRU t4LYttARD 'BDNDlNG AGENOY
,Q% ICOSI h
(w4
I h
1
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~
C.)
'0 O. BOX 013100, MIAMI, FL 33101 iyVVzi~
~rri. N.
FLORIDA POWER 8( LIGHT COMPANY March 15, 1979 L-79-61 Director of Nuclear Reactor Regulation Attention: Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stello:
,Re: St. Lucie Unit 1 Docket No. 50-335 Proposed Amendment to Facilit 0 eratin License DPR-67 In accordance with 10 CFR 50.30, Florida Power 8I Light Company submits herewith three (3) signed originals and forty (40) copies of a request to amend Appendix A of Facility'perating License DPR-67. A description of the proposed changes, followed by the revised Technical Specification pages, is attached.
The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power 5 Light Company Nuclear Review Board. They have concluded that it does not involve an unreviewed safety question.
Part of the material being proposed for inclusion in the Technical Specifications (Appendix A) is presently in the Environmental Technical Specifications (Appendix B). A proposed amendment to remove this material from the Environmental Technical Specifications is being prepared and will be forwarded to your office within a few weeks. We request that the two proposals be reviewed concurrently.
This amendment -is considered a Class III amendment per 10 CFR 170.22.
Accordingly, a check for four thousand dollars ($ 4,000.00) is enclosed.
Very tr 1 yours, obert E. Uhrig Vice President Advanced Systems & Technology 0 gP REU:MAS:cf ok
. Attachment cc: Mr. James P. O'Reilly, Region II 1I Mr. R. W. Zavadoski, Region II Harold F. Reis, Esquire 79OS l9Oalj'EOPLE... SERVING PEOPI.E
ATTACHMENT Re: St. Lucie Unit 1 Docket. No. 50-335 Proposed Tech Spec Change Ap endix I The objective of this proposal is to implement the requirements of 10 CFR 50, Appendix X. Draft guidance from the NRC was followed when appropriate, depending on the specific design and operation of St. Lucie Unit l.
For example, the solidification issue has not been addressed. At present, a waste solidification program is not in place at St. Lucie, however, the need for such a program is being evaluated and may lead to further correspondence.
0

ML17266A041

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Dear Mr. Stello:

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ML17266A041

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Dear Mr. Stello:

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Dear Mr. Stello:

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