ML20248C079
| ML20248C079 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/02/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20248C074 | List: |
| References | |
| NUDOCS 8906090253 | |
| Download: ML20248C079 (21) | |
Text
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'$ fj p, NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20553 o.....*
OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 122 License No. DPR-40
- 1. The Nuclear Regulatory Comission ('the Commission) has found that:
A. The application for amendment by the Omaha Public Power District (the licensee) dated January 6,1989 as supplemented on February 28, 1989, complies with the standards and requirements of the Atomic !
Energy Act of 1954, as anended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with' the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance: (i) that.the activities authorized by this amendment can be conducted without endangering the health and safety cf the public, and (ii) that such activities will be
. conducted in compliance with the Comission's regulations; D. The issuance of this license amendnent will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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G906090253 890602 PDR ADOCK 05000285 P PDC L - _ _ _ _ _ _ _ _ _ _ _ _ _ _
, i l
- 2. Accordingly, Facility Operating License No. DPR-40 is amended by changes I to the Technical Specifications as indicated in the attachment to this '
l license amendment, and paragraph 3.B. of Facility Operating License No.
DPR-40 is hereby amended to read as follows:
i B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.122 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective after 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1
D,nLA . b]Adn Frederick J. He ' don, Director Project Directorate - IV ,
Division of Re. actor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation L
Attachment:
Changes to the Technical Specifications
. Date of Issuance: June 2, 1989 i
a
, ATTACHMENTTOLICENSEAMEND!iENTNO.122 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 11 ii
- 3-0a
- 3-Ob
- 3-Oc 3-1 3-1 3-6 3-6 3-12a 3-12a 3-16c 3-16c 3-17 3-17
~
3-63 3-63 3-69 3-69 3-70 3-70 3-71 3-71' .
3-72 3-72 3-73 3-73 3-76 3-76 3-80 3-80 3-84 3-84
, TABLE OF CONTENTS (Continued)
Page 2.12 Control Room Systems..................................... 2-59 2.13 Nu clear Detector Cooling Sy stem. . . . . . . . . . . . . . . . . . . . . . . . . . 2-60 2.14 Engineered Safety Features System Initiation Instrumentation Settings............................... 2-61 2.15 Instrumentation and Control Systems...................... 2-65 2.16 River Leve1.............................................. 2-71 2.17 Miscellaneous Radioactive Material Sources............... 2-72 2.18 S hoc k Suppressors (Snubbers) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2-73 2.19 Fire Protection System................................... 2-89 2.20 Steam Generator Coolant Radioactive ty. . . . . . . . . . . . . . . . . . . . 2-96 2.21 Post-Accident Monitoring Instrumentation................. 2-97 2.22 Toxic Gas Monitors...................... ................ 2-99 I
3.0 SURVEILLANCE REQUIREMENTS................ ..................... 3-Da l 3.1 Instrumentation and Control.............................. 3-1 3.2 Equipment and Sampling Tests............................. 3-17 3.3 Reactor Coolant System and Other Components Subject to ASME XI Boiler and Pressure Vessel Code Inspection and Testing Surveillance........ 3-21 3.4 Reactor Coolant System Integrity Testing. . . . . . . . . . . . . . . . . 3-36 3.5 Containment Test......................................... 3-37 3.6 Safety Injection and Containment Cooling' -
l Syctems Tests.......................................... 3-54 3.7 Emergency Power System Periodic Tests. . . . . . . . . . . . . . . . . . . . 3-58 3.8 Main Steam Isolation Valves.............................. 3-61 3.9 Auxi l ia ry Feedwater Sys tem. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-62 3.10 Rea c to r Co re Pa rameters. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-63 3.11 Radiological Environmental Monitoring Programs........... 3-64
. 3.12 Radiological Waste Sampling and Monitoring............... 3-69 3.12.1 Liquid and Gaseous Effluents.................... 3-69 3.12.2 Solid Radioactive Waste......................... 3-71a 1
l 3.13 Radioactive Material Sources Surveillance............... 3-76 3.14 Shock Suppressors (Snubbers)............................. 3-77 3.15 Fire Protection System................................... 3-80 3.16 Recirculation Heat Removal System Integrity Testing...... 3-84 3.17 S team G e n e ra to r Tub es . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-86 4.0 DESIGN FEATURES................................................ 4-1 l 4.1 Site..................................................... 4-1 1 4.2 Containment Design Features.............................. 4-1 4.2.1 Containment Stru cture. . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.2.2 Penetrations.................................... 4-1 !
Containment Structure Cooling Systems. ... .. . ... . 4-2 4.2.3 1
l ii Amendment No. E#,ES,97,19#,122 i
r L ..
b , 3.0 SURVEILLANCE REQUIREMENTS 3.0.1 Each surveillance requirement shall be performed within the specified time interval with
- a. a maximam' allowable extension not to exceed 25% of the surveillance interval, and
- b. the combined time interval for any three consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.
3.0.2 The surveillance intervals are defined as follows:
Notation Title Frequency S Shift At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D Daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W Weekly At least once per 7 days BW Biweekly At least once per 14 days ;
M Monthly At least once per 31 days Q Quarterly At least once per 92 days SA Semiannual At least once per 184 days A Annually At least once per 366 days
'R Refueling At least once per plant operating cycle P Start up Prior to Re. actor Start up, if not completed in the previous week.
Exception to these intervals are stated in the individual i Specifications.
3.0.3 The provisions of Specifications 3.0.1 and 3.0.2 are applicable to all codes and standards referenced within the Technical Specifications. The requirements of the Technical Specifications shall have precedence over the requirements of the codes and standards referenced within the Technical Specifications.
3.0.4 Failure to perform a N rveillance Requirement within the allowed surveillance interval,. defined by Specifications 3.0.1 and 3.0.2, shall constitute noncompliance with the OPERABILITY requirements for the corresponding Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time i limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance Requirements do not have to be performed on inoperable equipment.
- l l
3-Da Amendment No.122 1
1
. 3.0 SURVEILLANCE REQUIREMENTS BASIS Specifications 3.0.1 through 3.0.4 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance Requirements stated in the Code of Federal Regulations,10CFR50.36(c)(3):
" Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting condition of operation will be met."
Specification 3.0.1 established the conditions under which the specified time interval for Surveillance Requirements may be extended. Item a.
permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities. Item b. limits the use of the provisions of item a to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Specification 3.0.1 are based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability demonstrated through actual surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.
The provisions of Specification 3.0.2 define the surveillance intervals for use in the Technical Specifications. This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications. A few surveillance requirements have unccmmon intervals, for example, Table 3-9 requires sampling of fish once per season. In such a case the surveillance interval shall be performed as defined by the individual specifications.
Specification 3.0.3 extends the testing interval required by codes and standards referenced by the Technical Specifications. This clarification is provided to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities. Under the terms of thic specification, the more restrictive requirements of the Technical Specifications take precedence over the codes and standards referenced therein.
l Specification 3.0.4 establishe3 the failure to perform a Surveillance l Requirement within the allowed surveillance interval, as defined by the provisions of Specifications 3.0.1 and 3.0.2, as a condition that constitutes a failure to meet the OPERABILITY require.ments for the corresponding Limiting Condition for Operation. Under the provisions 3-Ob Amendment t!o. 122 1
. . 3.0 SURVEILLANCE REQUIREMENTS Basis (continued) of this specification, systems and conr,onents are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable even though the Surveillance Requirements are met. This specifica-tion also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 3.0.4. However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification of 3.0.1, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. ,
Further, the failure to perform a surveillance within the provisions of Specification of 3.0.1 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the require-mentsof10CFR50.73(a)(2)(1)(B)becauseitisaconditionprohibited by the plant's Technical Specifications.
If the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shutdown is required to comply with the ACTION requirements, e.g., Specification 2.0.1, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> al'owance is provided to permit a delay in implementing the ACTION requirements.
This provides an adequate time limit to complete Surveillance Require-ments that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial ceasures would be required that may preclude completion of a surveillance.
The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform tho surveillance, and the safety significance of the delay in cenpleting the required surveillance. If a surveillance is not cepleted within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance, the time limits of the ACTION requirements are applicable at this time. When a surveillance is performed within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.
Surveillance Requirements do not have to be performed on inoperable equipment bect1se the ACTION requirements define the remedial measures that apply. However, the Surveillance Requirements must be met to demonstrate that inoperable equipment has been restored to operable l status. ,
3-Oc Amendment No.122
v, ..
4 .
-* * ' . 3. 0 SURVEILLANCE REQUIREMENTS 3.1 Instrumentation and Control I
j Applicability Applies to the reactor protective system and other critical instru-mentation and controls.
Objective To specify the minimum frequency and type of surveillance to be ;
applied to critical plant instrumentation and controls.
Specifications Calibration, testing and checking of instrument channels, reactor protective system and engineered safeguards system logic channels and miscellaneous instrument systems and controls shall be performed as specified in Tables 3-1 to 3-3.
Basis Failures such as blown instrument fuses, defective indicators, and faulted amplifiers which result in " upscale" or "downscale" indica-tion can be easily recognized by simple observation of the functioning of an instrument or system. Furthermore, such failures'are, in many cases, revealed by alarm or annunciator action and a check supple-ments this type of built-in surveillance.
Based on the District's experience in operation of conventional power plants and on reported nuclear plant experience, a checking frequency of once-per-shift is deemed adequate for reactor and steam system instrumentation. Calibrations are performed to ensure the presentation and acquisition of accuratq information.
The power range safety channels are calibrated daily against a ,
calorimetric balance standard to acccunt for errors induced by '
changing rod patterns and core physics parameters.
Other channels, subject only to the " drift" errors, can be expected to remain within acceptable tolerances if recalibration is performed at each refueling shutdown interval.
1 3-1 Amendment No. 9,122
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, 3.0 SURVEILLANCE REQUIREMENTS 3.2 Equipment and Sampling Tests Applicability Applies to plant equipment and conditions related to safety.
Objective To specify the minimum frequency and type of surveillance to be applied to critical plant equipment and conditions. Specifications Equipment and sampling tests shall be conducted as specified in Tables 3-4 and 3-5. Basis The equipment testing and system sampling frequencies specified in Tables 3-4 and 3-5 are considered adequate, based upon experience, to
. maintain the status of the equipment and systems so as to assure safe operation. Thus, those systems where changes might occur relatively rapidly are sampled frequently and those static systems not subject to changes are sampled less frequently. .
The control room air treatment system consists of high efficiency particulate air filters (HEPA) and the charcoal cdsorbers. HEPA filters are installed before the charcoal adsorbers to prevent' clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of iodine to the control room. The in-place test results will confirm system integrity and performance. The laboratory carbon sample tests results should indicate methyl iodide removal efficiency of at least 90 percent for expected accident conditions. The spent fuel storage-decontamination areas air treatment system is designed to filter the building atmosphere to the auxiliary building vent during refueling operations. The charcoal adsorbers are installed to reduce the potential release of radioicdine to the environment. In-place testing is performed to confirm the integrity of the filter system. The charcoal adsorbers are periodically sampled to insure capability for the removal of radioactive iodine. 3-17 Amendment No. If, 57,122
4
.. 2 3.0 SURVEILLANCE REQUIREMENTS 3.10 Reactor Core Parameters Applicability Applies.to reactor core parameters that affect shutdown margin, MTC,
~ linear heat rate and DNB margin.
Objective. To require evaluation of reactor core parameters. l -Specification
.(1) Shutdown Margin
- a. The shistdown margin shall be determined:
- 1. By verifying that the CEA group withdrawal _is above the '
Transient Insertion Limits of Specification 2.10.2 when-ever the reactor 1s in hot standby or power operation conditions at least once per shift, or
- 2. By considering the following factors whenever the re-actor is in hot or cold shutdown at least~once per day.
(i) Reactor coolant system boron concentration; (ii) CEA position; (iii) Reactor coolant system temperature;
, (iv) Fuel burnup; (v) Xenon concentration; and (vi) Samarium concentration.
- b. The overall core reactivity balance shall be compared to pre-dicted values to demo 6 strate agreement with i 1.0% Ak/k at least once per 31 F PC. The predicted reactivity values shall be adjusted (normalized) to correspond to the actual core con-ditions prior to exceeding a cycle burnup of 2000 MWD /MTU after each refueling.
3-63 Amendment No. 19, 20, 32, 122
. - 3.0 : SURVEILLANCE REQUIREMENTS 3.12 Radiological Waste Sampling and Monitoring 3.12.1 Liquid and Gaseous Effluents Applicability Applies to the sampling, monitoring, and testing used for liquid and
. gaseous effluents.
_ Objective To ensure that radioactive liquid and gaseous releases from the I facility arespecified the limits maintained as low as reasonably by Specifications 2.9.1 1) (achievable and 2.9.1(2).and within Specifications l I (1) Liquid Effluents ; a.- Radioactive liquid waste sampling and activity analyses shall be performed in accordance with Table 3-11. The results of. -! these analyses shall be used with the calculational methods in
. the ODCM to assure that the concentration at the point of release is limited to the values in Specification 2.9.1(1)a.
- b. Prior to release of each batch of liquid _ effluent, the batch l shall be mixed, sampled, and analyzed for pri'ncipal gamma. l enitters. When operational or other limitations preclude j
specific gamma radionuclides analysis of each batch, gross radioactivity measurements shall be made to estimate the quantity and concentrations of radioactive materials released in the batch, and a weekly sample composited from proportional aliquots from each batch released during the week shall be , analyzed for the principal gamma-emitting radionuclides. l
- c. The overboard header radiation monitor shall have a:
i (1) Source check prior to any release of radioactive l materials from the monitor or the hotel waste tanks. 1 (ii) Quarterly channel functional test. (iii) Channel calibration at refueling frequency. i
- d. The steam generator blowdown radiation monitors shall have:
)
(i) Daily channel checks. (ii) Monthly source checks. 4 i 3-69 Amendment No. 28, Sf, 122 i
~
3.0 SURVEILLANCE REQUIREMENTS 3.12 RadiologicalwastesamplingandMonitoring(Continued) 3.12.1' Liouid and" Gaseous Effluents (Continued) (iii) Quarterly channel functional tests. (iv) Channel calibration at refueling frequency. l
- e. The steam generator blowdown effluent flow rate will be calibrated at refueling frequency and visually determined I operable daily.
- f. Records shall be maintained of the radioactive concentrations and volume before dilution of each batch of liquid effluent released and of the average dilution flow and length of time over which each discharge occurred. Analytical results shall l be submitted to the Commission in accordance with Section 5.9.4.a of these' specifications.
(2) Gaseous Effluents !
- a. Radioactive gaseous waste sampling and activity analyses shall
. . be performed in accordance with Table 3-12. The results of these analyses shall be used with the calculational methods in the ODCM to assure that the concentration of radioactive i materials in unrestricted areas is 1imited to,the values in Specification 2.9.1(2)a.
b.- '(i) A ventilation stack radiation menitor shall have a source l check prior to any release of radioactive materials.from a gas decay tank or the containment. A monthly source check will be performed during refueling outages if a purge or gas decay tank release is not done during that month. , (ii) Each ventilation stack monitor shall have a quarterly channel functional test. (iii) Each ventilation stack monitor shall be calibrated at refueling frequency. l (iv) The ventilation stack flow rate will be calibrated and functionally tested at refueling frequency. The stack l radiation monitor flow rate will be calibrated and functionally tested at refueling frequency. Both will l i be determined operable by visual inspection daily. 1
- c. The condenser air ejector monitor shall have a:
(1) Daily channel check. (ii) Monthly source check. i 3-70 Amendment No. SS,122 1 a
3'. 0 SURVEILLANCE REQUIREMENTS
- .3.12 Liquid 3'12.1 Radiological Waste Sampling and Gaseous Effluents and Monitoring (Continued)
(Continued) (iii) Quarterly channel functional test. (iv.) Channel calibration at refueling frequency. l
- d. The hydrogen and oxygen monitoring system for the gas decay tanks shall have a:
(i) Daily channel check (when in service). (ii) Monthly cross comparison with a grab sample. (iii) Quarterly channel calibration using gas mixtures with concentrations in the range of interest. !
- e. Records shall be maintained and reports of the sampling and results of analyses shall be submitted to the Comission in accordance with Section 5.9.4.a of these specif M tions.
Basis The surveillance requirements given under Specification 3.12.1(2) provide assurance that radioactive gaseous effluents from the station are properly controlled and monitored over the life of the station in conformance with the requirements of General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A. These surveillance requirements provide the data for the licensee and the Commission to evaluate the performance of the station relative to radioactive gaseous wastes released to the environment. The existing minimum sensitivity of airborne effluent monitor RM-062 is SE-06 mci /cc/100 cpm and this minimum sensitivity shall be maiatained if the monitor is replaced. Reports on the quantities of the radioactive materials released in gaseous effluents shall be furnished to the Commis-sion on the basis of Section 5.9.4.a of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Comission may from time to time require the licensee to take such action as the Comission deems appropriate. The surveillance requirements given under Specification 3.12.1(1) provide assurance that liquid wastes are properly controlled and monitored in conformance with the requirements of General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A, during any planned release of radioactive materials in liquid effluents. These surveillance requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive liquid wastes released to the environ-ment. Reports on the quantities of radioactive materials released in liquid effluents shall be furnished to the Comission on the basis of Section 5.9.4.a of these Technical Specifications. On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Cor.raission may from time to time require the licensee to take such action as the Commission deems appropriate. 3-71 Amendment No. Ef, IRS,122 } L
1 A. [ ' TABLE'3-11' RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS
. A. . Monitor & Hotel Waste Tanks Releases Lower Limit of l, Type of Detection (LLD) j; Sampling Frequency Activity Analysis (4) (pCi/ml)
Each Batch Principal Gamma Emitters (2)(5) 5.0 E-07
^
I-131(2) 1.0 E-06 ' Monthly from One Dissolved Noble Gases (2) 1.0 E-05 Batch (Gamma Emitters) l Monthly Composite (1) H-3 1.0 E-05 ! Gross a 1.0 E-07 sQuarterly Composite (1) Sr-89, Sr-90 5.0 E-08 B. ' Steam Generator Blowdown Lower Limit of Type of Detection (LLD) Sampling Frequency Activity Analysis (4) (pCi/ml) Weekly Composite (1) Principal Gamma Emitters (5) 5.0 E-07 I-131(6) 1.0 E-06 Weekly (3) Dose Equivalent I-131 1.0 E-06 i (Gamma Emitters) Nonthly Dissolved Noble Gases 1.0 E-05 Monthly Composite (1) H-3 1.0 E-05 G" css a 1.0 E-07 Quarterly Composite (1) Sr-89, Sr-90 5.0 E-08 NOTES: ' (1) To be representative of the average quantities and concentrations of radioactive materials in liquid effluents, samples should be collected in proportion to the rate of flow of~the effluent stream. Prior to analyses, all samples taken for the composite should be mixed in order for the composite sample to be representative of the average effluent release. 3-72 Amendment No. 28, 86,122
... TABLE 3-11 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS (Continued) i NOTES: (2) Or gross radioactivity as described in Specification 3.12.1(1)b. (3) When steam generator iodine activity exceeds 50 percent of limits in Specification 2.20, the sampling and analysis frequency shall be increased to a minimum of five times per week. When the steam generator iodine activity exceeds 75 percent of this limit, the sampling and analysis frequency shall be increased to a minimum of once per day. (4) The lower limit of detection (LLD) is defined in the ODCM based on NUREG
.0472, Rev. 3.
(5) The principal gamma emitters for which the LLD specification applies exclusively ~are the following radionuclides: Mn-54, Fe-59 Co-58, Co-60, 2n-65, Mo-99, Cs-134 Cs-137, Ce-141 and Ce-144.
.(6) A weekly. grab sample and analyses program including gamma isotopic identification will be initiated for the turbine building sump effluent when the stear generator blowdown water composite analysis indicates the I-131concentrationisgreaterthan1.0E-06 microcurie / milliliter.
3-73 Amendment No. 28. ES,122 . I
, 3.0 SURVEILLANCE REQUIREMENTS 3.12 RADI0 ACTIVE MATERIAL SOURCES SURVEILLANCE Applicability Applies to leakage testing of byproduct, source, and special nuclear radioactive material sources. Objective To assure that leakage from byproduct, source, and special nuclear radioactive material sources does not exceed allowable limits. Specification Tests for leakage and/or contamination shall be performed by the licensee or by other persons specifically authorized by the NRC or an agreement State, as follows:
- 1. Each sealed source, except startup sources subject to core flux, containing radioactive material, other than Hydrogen 3, with a
. half-life greater than thirty days and in any form other than gas shall be tested for leakage and/or contamination at intervals of six months. l
- 2. The periodic leak test required does not apply to' sealed sources that are stored and not being used. 'The sources excepted from this test shal1 be tested for leakage prior to any use or transfer to another user unless they have been leak tested within six months prior to the date of use or transfer. In the absence of a certificate from a transferor indicating that a test has been made within six months prior to the transfer,
. sealed sources shall not be put into use until tested.
- 3. Startup sources shall be leak tested prior to and following any repair or maintenance and before being subjected to core flux.
3-76 Amendment No. II,122
,A'
~
. 3.0' SURVEILLANCE REQUIREMENTS 3'.15 Fire Protection System Applicability' Applies to fire detection and fire extinguishing subsystems in nuclear safety related areas and other areas which may impact on safety related systems.
Objective To ensure the operability of the fire protection system in nuclear safety related systems. j Specifications (1) Each fire detector listed in Table 2-7 and in containment shall be demonstrated operable:
- a. At least once per 6 months by performance of a channel functional test and a test of the supervision circuitry.
- b. Testing interval for fire detectors which are inaccessible due to high radiation or require an equipment alignment not used in power operation may be extended until such time as the detectors become accessible for a' minimum of 36 hours. However, the shutdown need not be extended solely for the purpose of this testing. Such detectors shall be functionally tested at a maximum interval of once per refueling cycle.
i (2) The fire suppression water system shall be demonstrated operable:
- a. At least once per month by starting each, pump and operating it for at least 15 minutes.
- b. At least once per month by verifying that each valve in the flow path is in itc correct position.
- c. At least once per 12 months by cycling each testable valve (those which can be cycled without endangering the safety of equipment) in the flow path through at >
least one complete cycle of full travel. I d. At least once per 18 months by performing a system func- )
- tional test which includes
1 1. Verifying that each pump develops at least 1800 l gpm at a system head of 260 feet.
- 2. Cycling each valve in the flow path that is not testable during plant operation through at least one complete cycle of full travel, and 3-80 Amendment No. # , 122
ll l L . l- . l 1 l .. j 3.0 SURVEILLANCE REQUIREMENTS 3.16 Recirculation Heat Removal System Integrity Testing Applicability 1 Applies to determination of the integrity of the shutdown cooling ) system and associated components. Objective 1 To verify that the leakage from the recirculation heat removal system components is within acceptable limits. Specifications (1) a. The portion of the shutdown cooling system that is outside the containment shall be tested at 250 psig or a refueling-interval,
- b. Piping from valves HCV-383-3 and HCV-383-4 to the discharge isolation valves of the safety injection pumps and containment
. spray pumps shall be hydrostatically tested at no less than 100 pMg at the testing frequency specified in (1)a. above.
- c. Visual inspection of the system's components shall be per-formed at the frequency specified in (1)a. ab'ove.to uncover any significant leakage. The leakage shall be measured by collection and weighing or by any other equivalent method.
(2) a. The maximum allowable leakage from the recirculation heat removal system's components (which include valve stems, flanges, and pump seals) shall not exceed one gallon per minute, under the normal hydrostatic head from the SIRW tank.
- b. Repairs shall be made as required to maintain leakage j within the acceptable limits.
Basis The limiting leakage rates from the shutdown cooling system are judgment values based primarily on assuring'that the components could operate without mechanical failure for a period on the order of 200 days after a design basis accident. Thetestpressure(250 psig) achieved either by normal system operation or by hydrostatic testinggivesanadequatemarginoverthegghestpressurewithin the system after a design basis accident. Similarly, the hydrostatic test pressure for the return lines from the contain-ment to the shutdown cooling system (100 psig) gives an adequate margin over the highest pressure within the lines after a design basis accident. 3-84 Amendment No. 77,122 - _ _ _ _ _ _ _}}