ML18092A494

Proposed Tech Spec Changes Re Radioactivity Inventory Limit

ML18092A494
Person / Time
Site:	Salem
Issue date:	02/08/1985
From:	Public Service Enterprise Group
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ML18092A493	List: ML18092A492 ML18092A494
References
NUDOCS 8502200416
Download: ML18092A494 (13)

Text

TABLE 3.3-12 (Continu~d)

TABLE NOTATION ACTION 26 - With th~ number of channl'!ls OPERABLE less than required by the Minimum Channl'!ls OPERABLE requireml'!nt, effluent*rl'!ltl!ases may continue provided that prior to initiating a rell'!ase:

a. At least two independent samples are analyzt'l!d in accordancl'!

with Specification 4.11.1.1.1, and

b. At least't\t.U tl'!chnically qualified ~mbers of thl'! Facility Staff independently verify the release rate calculations and discharge linl'! valving; Otherwise, suspend rl'!lease of radioactive efflu~nts via this pathway.

ACTION 27 - With the numbl'!r of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releasl'!s via this pathway may continut'I! provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least lo-7 microcuril'!s/gram:

ao At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE ECUIVALENT I-131.

b. At least once per 2~ hours when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/

gram DOSE ECUIVALENT I-131.

ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, l'!ffluent releases via this pathway may continue provided that:

a. With a Service Water System leak on the Containment Fan Coil Unit associated with the inoperable rronitor either:

1. Grab samples are to bl"! collected and analyzed for gross activity (beta or gamma) at a limit of detection of at least 10-7 uCi/gram at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or

2. Isolate the release pathway.

b. With no identified service water leakage on the Contain~nt Fan Coil Unit associated with the inoperable rronitor, collect grab samples and analyze for gross radioactivity (beta or gamma) at a limit of detection of at least io-7 uCi/gram at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. '

• SALEM - UN IT 1 3/4 3-60 r

I 0502200416 050200 PDR ADOC~ 05000272 I!

I p PDR

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONOITIONAFOR OPERATION 3.11.l.6 The quantity of radioactivity contained in each g storage tank shall be limited .to 36,000 curies noble.gases (considered as Xe- 33).

APPLICABILITY: At all times.

'ACTION: -.

a. te

• l in any gas storage tank spend all additions of w thin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQ~IREMENTS 4.11.2.6 The quantity of r tank shall be determined t tive material contained in each gas storage ithin the above limit at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> D when radioactive material re being added to the tank.

SALEM - UNIT l 3/4 "ll-15 Amendment No. 59

THIS PAGE INTENTIONALLY BIANK SALEM - UNIT 1 3/4 11-16

TABLE 3.3-12 RADIOACTIVE LIQJID EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS INST~UMENT OPERABLE ACTION

1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (2-Rl8} 1 26

b. Steam Generator Blowdown line 4 27

{2-Rl9 A, B, C, and D}

2. GROSS RADIOACTIVITY MONITORS NOT PROVIDING*AUTOMATIC TERMINATION OF RELEASE

a. Containment Fan Coolers - Service Water Line 3 28

{2-Rl3_A, B, C) Discharge

b. Chemical Waste Basin Line (R37) l 31

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid_Radwaste Effluent Line 1 29

b. Steam Generator Blowdown Line 4 29

4. TANK LEVEL INDICATING DEVICES

a. Temporary Outside Storage Tanks as Required 1 30

TABLE 3.3-12 (Continued}

TABLE NOTATION ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue provided that prior to initiating a release:

a. At least t'I<<> independent samples are analyzed in accordance with Specification 4.11.1.1.1, and

b. At least t'I<<> technically qualified members of the Facility Staff independently verify the rel ease rate cal cul at ions and

_discharge line valving; 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 provided grab samples are analyzed for gross radioactivity (beta or gamma) at a 1imit of detection of at least io-7 microcuries/gram:

a. At least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the specific activity of the secondary coolant is greater than 0.01 microcuries/gram DOSE EQJIVALENT I-131.

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/

gram DOSE EQJIVALENT I-131.

ACTION 28 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that:

a. At least once per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.s, local nnnitor readouts for the affected channels are verified to be below their alarm setpoints, or

b. With a Service Water System leak on the Containment Fan Coil Unit associated with the inoperable r.nnitor either:

1. Grab samples are to be collected and analyzed for gross radioactivit}'. (beta or gramma) at a limit of .detection of at least 10-7 uCi/gram at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or

2. Isolate the release pathway.

c. With no identified service water leakage on the Containment Fan Coil Unit associated with the inoperable nnnitor collect-grab samples and analyze for gross radioactivity (beta or gamma) at a limit of detection of at least io-7 uCi/gram at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SALEM - UNIT 2 3/4 3-55

TABLE 3.3-12 {Continuedf TABLE NOTATION ACTION 29 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. Pump performance curves may be used to estimate flow.

ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, liquid additions to this tank may continue for up to 30 days.provided the tank liquid level is estimated during all liquid additions ~o the tank.

ACTION 31 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided that sampling is conducted in accordance with the following table:

Frequency Conditio.n l/week During normal operation (all MODES) 1/oay During operation with an identified primary to secondary leak on either Salem Unit.

SALEM - UNIT 2 3/4 3~56

_)

RADIOACTIVE EFFLUENTS GAS STORAGE TANKS LIMITING CONDITION FOR OPERATION each gas storage tank shall as Xe-133) e APPLICABILITY: At a11 times.,

ACTtON:

a. With th~ quantity o material in any gas storage tank exceeding the above 1 d1ate1y suspend all add1t1ons of radtoact1ve material ank and within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> reduce the tank contents to within t be The prov1s1o at1ons 3.0.3 and 3e0*4 are nat applicable.

- 4ell.,2.6 The quant1 contained in each gas storage tank shall be dete 1n to be within the above 11m1t at least. once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when* rad1 oa'ct he ter1 a s are be1 ng added to the tank

• I SALEM ~ UNIT 2 3/4 11-16 Amendment No. 28

THIS PAGE INTENI'IONALLY BLANK SALEM .;.. UNIT 2 3/4 11-16

ATTACHMENT 2 RE-EVALUATION OF THE RADIOACTIVITY INVENTORY LIMIT FOR A WASTE GAS DECAY TANK - SALEM GENERATING STATION The current technical spedif ication limit on the radioactivity inventory for a single waste gas decay tank (Technical Specification 3.11.2.6) is 36,000 curies, xe-133 equivalent.

Based on the calculational method of NUREG-0133, Section 5.6.1, this limit was conservatively determined considering xe-135 as the controlling radionuclide instead of xe-133. Based on the xe-133 equivalent criterion of NUREG-0133, Section 5.6.1, the appropriate radioactivity limit for a WGDT is 2.23 x 105 curies.

This increase in the WGDT curie limit of a factor of 6.2 (i.e.,

223,000/36,0~0) is explained simply as the ratio of xe-135 dose factor (gamma, total body) to the_xe-133 dose factor (gamma, total body). The meteorological dispersion used for these calculations was the NRC's design base accident X/Q included in Salem SER, Unit 2 (i.e., X/Odba, = 2.4 x lo-4 sec/m3). This value represents the 0-2 hour time period, which is appropriate for evaluating a WGDT failure.

The calculational method of NUREG-0133, Section 5.6.1, is

• inconsistent in the application of the definition of xe-13j equivalent. Determination of xe-133 equivalent radioactivity limit for a WGDT should be calculated considering Xe-133 as the only isotope. Therefore, the appropriate value for the WGDT limit for Technical Specification 3.11.2.6 is the 2.23 x 105 curies, as determined above.

The calculational method of NUREG-0133, Secti9n 5.6.1, is appropriate for determining a total activity limit considering a radionuclide distribution, it is not representative of a Xe-133 equivalent limit. For evaluating compliance with a xe-133 equivalent limit, the Xe-133 equivalent quantity based on a radionuclide distribution is determined by the following equation:

Oxe-133 = Oi x DFi DFxe-133 Where Oxe-133 = Xe-133 equivalent quantity Qi = Quantity of radionuclide i*~

DFi = dose factor for radionuclide i~

DFxe-133= dose factor for Xe-133 As the attached evaluation demonstrates, a WGDT limit of 2.23 x 105 curies is far in excess of an inventory that could be attained in any single WGDT considering other, more restrictive technical specification limits (e.g., primary coolant radioactivity limits). Based on this evaluation, the radioactivity limit of Technical Specification 3.11.2.6 is not a limiting criterion and consequently unnecessary as a technical.

specification limit. Having to perform periodic surveillance to verify compliance with a non-restrictive technical specification limit imposes an unnecessary burden on plant operating personnel.

Technical Bases for Eliminating c~rie Inventory Limit for Gaseous waste Decay Tanks The NRC Standard Technical Specifications include a limit for the amount of radioactivity that can be stored in a single waste gas decay tank. This curie inventory limit i.s established to assure that in the event of a tank failure releasing the radioactive content to the environment the resulting*total body dose at the site boundary would not exceed 0.5 rem.

For the Salem Generating Station, allowable primary coolant radioactivity concentration is established by an Appendix A Technical Specification (T.S. 3.4.~ for Unit 1 and T.S. 3.4.9 for Unit 2) which limits the primary coolant radioactivity concentrations to 100/E uCi/gram with E. being the average beta and gamma energy per disintegration (in MeV) for isotopes, other than iodines, with half lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

This equation yields an upper primary coolant gross activity limit of about 182*uCi/ml of Xe-133 equivalent concentration.

By applying this activity concentration l.imit to the total liquid volume of the primary system, a total activ*ity limit can be determined. For Salem, the primary system volume is about 94,000 gallons, which yields a possible total inventory of approximately 73,000 curies.

By assuming a typical radionuclide disq:"ibution, an equivalent Xe-133 inventory can be determined. Table 1 provides the typical radionuclide (noble gases) distribution and the xe-133 equivalent concentration. For determining concentration in a waste gas decay tank, a conservative assumption of 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> for degassing the primary system has been used to decay correct the primary coolant concentrations (based on degassing the total primary system via the VCT with a normal letdown flow of 75 gpm) e The equivalent concentration is determine<] by multiplying the decayed radionuclide concentration by the ratio of the radionuclide total body dose factor to the Xe-133 total body dose factor. Summing all the individual radionuclide equivalent concentrations provides the overall Xe-133 equivalent concentration. The data shows that the equivalent concentration (decay corrected) is 'less than the gross concentration (i.e.,

211 uCi/g total in primary coolant versus 182 uCi/g equivalent). The resulting maximum po.ssible Xe-133 equivalent curie inventory for WGDT input is thus approximately 73,000 Ci.

f' Table 1 I Xe-133 Effective Concentration I

I Primary* Half-life Concentratioo Reg Guide 1.109 Ratio Xe-133 Coolant @ 20 hr decay TB lbse Factor '1'8-DF Equivalent Cone (uCi/g) (uCi/ml) 'mrem/yr Xe-133 DF @ 20 hr decay pei/m-> (uCi/ml)

Kr-85M 4.5 hr . 1.2 x lo-3 II 1.7 4.1 Kr-85 3.9 10.7 yr 3.9 1.6 x lo-5 0.06 Kr-87 0.9 76.3 min 5.2 x lo-3 20.

Kr-88 2.7 2.84 hr 1.5 x 10-2 52.

Xe-133M 2.1 2.2 days 1.6 2.5 x lo-4 0.86 1.4 Xe-133 194. 5.3 days 174. 2.9 x lo-4 1.0 174 Xe-135M 0.1 16 min 3.1 x io-3 11.

Xe-135 5.4 9.1 hr 1.2 1.8 x lo-3 6.2 7.4 Xe-138 0.5 17 min 0.0 x io-3 30

'lbtal 211 181 182

• Adapted from the Salem FSAR Update, Table 11.1-8, July 22, 1982, for a 1% fuel failure ccnditim. (The radioactivity ccncentration far the naninal 0.1% failed fuel level used by the NRC fOI'." evaluating canpliance with the design criteria of Appendix I to 10 CFR 50 can be app:-oxirnated by reducing the above values by a factor of 10.)