ML18113A826
| ML18113A826 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/05/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 411C-071078, 411C-71078, NUDOCS 7902080236 | |
| Download: ML18113A826 (16) | |
Text
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VIRGINIA ELECTRIC.AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 5, 1979 Mr. Harold Ro Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. A. Schwencer, C~ief Operating Reactors Branch No.
Divisi6n of Operating Reactors Uo*S. Nuclear Regulatory C~mmission Washi.ngton, DC 20555
Dear Mro Denton:
Serial No. 411C/071078 LQA/JEE:esh Docket Nos. 50-280 50-281 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS SURRY:POWER STATION In response to Mr6 Schwencer 1s letter of January 25, )979, the enclosed radiological effluent changes to the Surry 1 and 2 Technical Specifications are provided at thi's time for review.
The attached specifi-cations contain portions of the anticipated modifications to Sections 1, 3a7, 3o 11, and 469.
These changes have not been reviewed by the Station or System Nuclear Safety and Operaiing Committeeso As discussed with Mro Don Neighbors, the Surry project manager, it is intended that the complete appl icatio~ for license amendment will be provided by February 28, 1979.
cc:
Mro James Po 0 1Reilly~ Director Office of Inspection and Enforcement R.eg ion 11 r
Very truly yours,
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- Co *.Mo Sta 11 id,gs Vice President-Power Supply and Production Operations 7902080)..3~~
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TS 1.0-4 other independent channels measuring the same variable.
- 2.
Channel Functional Test Injection of a simulated signal into an analog channel or makeup of the logic combinations in a logic channel to verify that it is operable, including alarm and/or trip initiating action.
- 3.
Channel Calibration Adjustment of channel output such that it responds, with acceptable range and accuracy, to known values of the parameter which the chan-nel measures.
Calibration shall encompass the entire channel, including equipment action; alarm, or trip, and shall be deemed to include ~he channel functional test.
- 4.
Source Check A Source Check shall be the qualitative assessment of radiation monitor response when the channel sensor is exposed to a radioactive source.
H.
Containment Integrity Containment integrity is defined to exist when:
- 1.
All non-automat~c containment isolation valves, except those required.
for intermittent operation in the performance of normal operational activities, are locked closed and under administrative control.
Non-automatic containment isolation valves may be opened intermittently for operational activities provided that they are under administrative control and are capable of being closed iTILmediately if required.
e TS 1.0-5
- 2.
Blind flanges are installed where required.
- 3.
The equipment access hatch is properly closed and sealed.
- 4.
At least one door in the personnel air lock is properly closed and sealed.
- 5.
All automatic containment isolation valves are*operable or are locked closed under administrative control.
- 6.
The uncontrolled containment leakage satisfied Specification 4.4.
I.
Reportable Occurrence
- 1.
Definition:
Refer to Technical Specification 6.6, Station Reporting Requirements for the definitions and examples of the two categories of Reportable Occurrence Reports*
- a.
Prompt Notification With Written Follow-up.
- b.
Thirty Day Written Reports J.
Quadrant Power Tilt The quadrant power tilt is defined as the ratio of the maximum upper excore detector current to the average of the upper excore detector currents or the ratio of the maximum l~wer excore detector current to the average of the r
lower excore detector currents whichever is greater.
If one excore detector is out of service, the three inservice units are used in computing the
- average.
e TS
- 1. 0-6 K.
Low Power Physics Tests Low Power Physics Tests conducted below* 5% of rated power which measure fundamentals characteristics of the core and related instrumentation.
L.
Fire Suppression Water System
./
A Fire Suppression Water System shall consist of:
a water source(s);
gravity tank(s) or pump(s); and distribution piping with associated sectionalizing control or isolation valves.
Such valves shall include yard hydrant curb valves, and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe or spray system riser.
M.
Offsite Dose Calculation Manual (ODCM)
An Offsite Dose Calculation Manual shall be a manual containing the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm/trip setpoints.
Requirements of the ODCM are provided in Speci-fication (
).
1
e TS 3.7-1 3.7 INSTRUMENTATION SYSTEMS Operational Safety Instrumentation Applicability:
Applies to reactor and safety features instrumentation systems.
Objectives:
To provide for automatic initiation of the Engineered Safety Features in the event that principal process variable limits are exceeded, and to delineate the conditions of the plant instrumentation and safety circuits necessary to ensure reactor safety.
Specification A.
For on-line testing or in the event of a subsystem instrumentation channel failure, plant operation at rated power shall be permitted to continue in accordance with TS Tables 3.7-1 thro"ugh 3.7-3.
B.
In the event the number of channels of a particular subsystem in service falls below the limits given in the column entitled Minimum Operable Channels, or Minimum Degree of Redundancy cannot be achieved, operation shall be limited according to the requirement shown in.
Column 4 of lS Tables 3.7-1 through 3.7-3.
C.
In the event of subsystem instrumentation channel failure permitted by specification 3.7-B, TS Tables 3.7-1 through 3.7-3 need not be observed during the short period of time the operable subsystem channels are tested where the failed channel must be blocked to*
prevent unnecessary reactor trip.
e TS
- 3. 7-.2 D.
The Engineered Safety Features initiation instrumentation setting limits shall be as stated in TS Table 3.7-4.
E.
Automatic functions operated from radiation monitor alarms shall be as stated in TS Table 3.7-5.
F.
The radioactive effluent process and monitoring instrumentation channels shown in Table shall be operable with their alarm/trip setpoints set to ensure that the limits of Specifica-tions are not exceeded.
- 1.
.With a radioactive effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of Specifications 3.11.A & Bare met, immediately suspend the release of radioactive effluents monitored by the affective channel or declare the channel inoperable.
el
- 2.
- With one or more radioactive effluent monitoring instrumentation channels inoperable, take the Action shown in Table~~~--*
- 3.
The radioactive effluent monitoring setpoints shall be determined in accordance with the ODCM.
An auditable record of the setpoint calculations shall be maintained.
e TS 3.11-1 3.11 EFFLUENT RELEASE Applicability:
Applies to the controlled release of radioactive liquids and gases from the station.
Objective:
To establish conditions by whicl). gaseous and liquid wastes containing radioactive materials may be released, and to assure that all such releases are within the concentrations specified in 10 CFR 20.
In addition, to assure that the releases of liquid and gaseous radioactive wastes to unrestricted areas are as low as reasonably ach:levable as set forth in Appendix I to 10 CFR 50.
Specification A.
Liquid Effluents
- 1.
Concentration
- a.
The concentration of radioactive material released at any-time from the site to unrestricted areas (See Figure 3.11.1) shall be limited to the concentrations specified in 10 CFR 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained i1oble gases, and tritium.
For dis-solved or entrained noble gases and tritium, the concentration shall be limited to 2 x 10-4 µCi/ml total activity.
- b.
With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, inunediately restore concentration within the.above limits and
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TS 3.11-2 provide prompt notification to the Commission pursuant to Specification 6.6.2.a.
- 2.
Dose
- 3.
- a.
The dose or dose commitment to an individual from radio-active materials in liquid effluents released to unrestricted areas (See Figure 3.11.1) shall be limited during any calendar quarter to< 1.5 mrem to the total body and to 2 5 mrem.to any organ,
- b.
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;6.2.b, Thirty Day Written Report which identifies the cause(s) for exceeding the limit(s) and defines the corrective actions.
Liquid Waste Treatment
- a.
The appropriate subsystems of the Liquid Radwaste Treatment System shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected t dose due to liquid effluent releases to unrestricted *areas (See Figure 3.11.1) when averaged over 31 days would exceed 0.25 mrem to the total body or 0.8 mrem to any organ.
- b.
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 6.6.2.b, a Thirty Day Writter._ Report which
~ TS 3.11-3 includes the following information:
- 1) Identification.of equipment or subsystems not Operable and the reason in-operability, 2) Action(s) taken to r~store the inoperability equipment to Operable status, and 3) Summary description of action(s) taken to prevent recurrence.
B.
Gaseous Effluents
- 1.
Dose Rate
- a.
The instantaneous dose rate in unrestricted areas.(See Figure 3.11.1) due to radioactive materials released in gaseous efflu-ents from the site shall be limited to the follm/ing values:
- 1) The dose rate limit for all noble gases shall be< 500 mrem/
yr to the total body and< '3000 mrem/yr to the skin, and
- 2) The dose rate li~it for all radioiodines and for all radio-active 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..
- b.
With the dose rate(s) exceeding the above limits, immediately decrease the release rate, to comply with the limit(s) and provide prompt notificat.ion to the Commission pursuant to sp*ec:i,fication 6. 6. 2. a.
- 2.
Dose, Noble Gaseous
- a.
The air dose per reactor in unrestricted areas (See Figure 3.11.1) due to noble gases released in gaseous effltients shall be limited to< 5 mrad for gamma radiation and< 10 mrad for beta radiation during any calendar quarter.
- 3.
- b.
TS 3.11~4 Wi~the circulated air dose from ~release of radioactive materials in gaseous effluents exceeding any of the above limits, prepare, and submit to the Commission within 30 days, pursuant to Specification 6.6.2.b a Thirty Day Written Report which includes _the following information:
- 1) Identification of equipment or subsystems not Operable and the reason for inoperability, 2) Action(s) taken to restore the inoperable equipment to Operable status, and 3) Sum~ary description of action(s) taken to prevent recurrence.
Dose, Radioiodines, Radioactive Material in Particulate Form, and Radionuclides other than Noble Gases.
- a.
The dose per reactor 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< 7.5 mrem during any calendar quarter.
- b.
With the calculateq. dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding the above limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.6.2.b, a Thi.rty Day Written Report which identifies the causes of such release, and:Juhe corrective action to be taken:
- 4.
Gaseous Radwaste Treatment
- a.
The appropriate subsystems of the Gaseous Radwaste Treatment System shall be used to reduce radioactive materials in
"'gasecius waste prior to their dischai"g~ when th~ projected doses
- 5.
e TS 3.11-5 due to effluent releases to unrestricted areas (See Figure 3.11.1) when averaged qver 31 days exceeds O. 8 mrad for gamma radiation, 1.6 mrad for beta radiation, or 1.2 m~em to any organ.
- b.
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 ~o Specification 6.6.2.b, a thirty day written report written report which includes the following information:
- 1) Identi-
_fication of equipment or subsystems not Operable and the reason for inoperability; 2) Action(s) taken to restore the inoperable equipment to Operable status; and 3) Summary description of action(s) taken to prevent a recurrence.
Gas Storage Tanks
- a.
The quantity of radioactivity contained in each gas storage tank shall be limited to< 26,700 curies noble gases (con-sidered as Xe-133).
- b.
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 houri either reduce the tank contents to within the limit or provide prompt notification to the Commission pursuant to Specification 6.6.2.a.
The written follow-up report shall include a description of activities planned and/or taken to reduce the tank contents to within the above limit.
e TS 4.9-1 4.9 EFFLUENT SAMPLING AND RADIATION MONITORING SYSTEM Applicability:
Applies to the periodic monitoring and recording of radioactive effluents.
Objective:
To ensure that radioactive releases are maintained as low as practicable and within the limits set forth in 10 CFR 20 and Appendix I to 10 CFR 50.
. Specification A.
Liquid Effluents
- 1.
Concentration
- a.
The concentration of radioactive material at any time in liquid effluents released from the site shall be continuously monitored in accordance with Table 3.7-5.
- b.
The liquid effluent continuous monitors having provisions for automatic termination of liquid releases, as listed in Table 3.7-5, shall be used to limit the concentration of radiq.active material released at any time from the site to unrestricted areas to the values given in Specification 3.11.A.1.
- c.
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 4.9-2.
~ TS 4.9-2
- d.
Post-release analyses of samples from batch releases shall be performed in accordance with Table 4.9-2.
- e.
The radioactivity concentration of liquids discharged from continuous release points shall be determined by collection and analysis of samples in accordance with Table 4. 9-2.
- f.
Reports.
The annual Radioactive Effluent Release Report shall include the information specified in Specification
- 6. 6-3. b (1).
- 2.
Dose
- 3.
- a.
Dose Calculations.
Cumulative dose contributions from liquid effluents shall be detennined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once per 31 days.
- b.
Reports.
The annual Radioactive Effluent Rele~se Report shall in.elude the information specified in Specification 6.6-3.b(l).
Liquid Waste Treatment
- a.
Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days.
- b.
The liquid radwaste system shall be demonstrated OPERABLE at least once per 92 days unless the liquid radwaste system has been utilized to process radioactive liquid effluents during the previous 92 days.
e TS 4.9-3 B.
Gaseous Effluents
- 1.
Dose Rate
- a.
The release rate, at any time, of noble gases in gaseous effluents shall be controlled by the offsite dose rate as established in Specification 3.11.B.1.
- b.
The noble gas effluent continuous monitors having provisions for the automatic termination of gaseous releases, as listed in Table 3.7-5, Specification 3.li.B.l, when monitor setpoint values are exceeded.
- c.
The release rate of radioactive mate'rials, 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 l1. 9-3.
- d.
The dose rate in unrestricted areas, due to radioactive ma-terials,other than noble gases,released in gaseous effluents, shall be determined to be within the required limits by using the results of. the sampling and analysis program, specified in Table 4.9-3, in performing the calculations of dose rate in unrestricted areas.
- e.
Reports.
The annual Radioactive Effluent Release Report shall include the information specified in Specification 6.6-3.b(l).
- 2.
Dose, Noble Gases
- a.
Dose Calculations.
Cumulative dose contributions for the
r*
- 3.
e TS 4.9-4 total time period shall be determined in accordance with the Off site Dose Calculation Manual (ODCM) at least once every 31 days.
- b.
Reports.
The annual Radioactive Effluent Release Report shall include the information specified in Specification 6.6-3.b(l).
Dose, Radioiodines, Radioactive Material in Particulate Form, and Radionuclides Other Than Noble Gases
- a.
- Dose Calculations.
Cumulative dose contributions for the total time period shall be determined in accordance with the ODCM at least once every 31 days.
- b.
Reports.
The annual Radioactive Effluent Release Report shall include the information specified in Specification 6.6-3.b(l).
- 4.
Gaseous Radwaste Treatment
- 5.
- a.
Dose due to gaseous releases to unrestricted areas shall be projected at least once per 31 days.
- b.
The appropriate systems shall be demonstrated OPERABLE at least once per 92 days unless the appropriate system has been utilized to process radioactive gaseous effluents during the previous 92 days.
Gas Storage Tanks
- a.
The quantity of radioactive material contained in each gas storage tank shall be determined to be within the. limit
TS 4.9-5 established in Specification 3.11.B.5 at least monthly when radioactive materials are being added to the tank.
C.
RESERVED D.
All radiation monitor channels shall be checked, calibrated; and tested as indicated in Table 4.1-1.
E.
The environmental program given in Table 4.9-1 shall be conducted.
F.
A census of animals producing milk for human consumption shall be conducted at the beginning and at the middle of the grazing season to determine their location and number with respect to the site.
The census shall be conducted under the following conditions:
- 1.
- 2.
Within a 1-mile radius from the plant site or within the 15 mrem/yr isodose line, whichever is larger, enumerated by a door-to-door or equivalent counting technique.
Within a 5-mile radius for cows and a 15-mile radius for goats, enumerated by using referenced information from country agricul-tural agents or other reliable sources.
If it is learned from this census that animals. are present at a loca-tion which yields a calculated thyroid dose greater than from previously sampled animal~, the new location shall be added to the surveillance program as soon as practic *.,e.
The sampling location having the lowest calculated dose may then be dropped from the surveillance pro-gram at the end of the grazing season during which the census was con-ducted.
Also, any location from which milk can no longer be obtained may be dropped from the surveillance program after notifyl.,,;, the NRG in writing that milk-producing animals are no longer present at that location.