Text

Replacement Pages to Amends 63 & 35 to Licenses DPR-70 & DPR-75,respectively & Replacement Pages to Amend 36 to License DPR-75
	ML20128K446
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Site:	Salem
Issue date:	06/21/1985
From:	; NRC
To:	;
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ML20128K451	List: ML20128K446;
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8 It i

8 TABLE 3.3-12

.117 E8 y

RADIDACTIVE LIQJID EFFLUENT MONITORING INSTRUMENTATION 9

>h ylu MINIMUM CHANNELS INSTRUMENT OPERABLE ACTION b

1.

GROSS RADI0 ACTIVITY MONITORS PROVIDING AUTOMATIC 1

TERMINATION OF RELEASE ssM a.

Liquid Radwaste Effluent Line (2-R18) 1 26

.b.

Steam Generator Blowdown Line 4

27 (2-R19 A, B, C, and D) 2.

GROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC w1 TERMINATION OF RELEASE a.

Containment Fan Coolers - Service Water Line 5

28 (2-R13 A, B, C) Discharge i

b.

Chemical Waste Basin Line (R37) 1 31 3.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line 1

29 b.

Steam Generator Blowdown Line 4

29 5

4.' TANK LEVEL INDICATING DEVICES t

z a.

Temporary Outside Storage Tanks as Required 1

30

TABLE 3.3-12 (Continued)

TABLE NOTATION ACTION 26 - Withi 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 two independent samples are analyzed in accordance with Specification 4.11.1.1.1, and b.

At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, :uspend 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 radjoactivity (beta or gamma) at a limit of detection of at least 10- microcuries/ gram:

~

a.

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 greater than 0.01 microcuries/ gram DOSE EQJIVALENT I-131.

b.

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 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 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , local penitor 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 conitor either:

1.

Grab samples are to be collected and analyzed for gross radioactivity (beta or gramma) at a limit of detection of at least 10-' uCi/ gram at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or 2.

Isolate the release pathway.

c.

With no identified service water leakage on the Containment Fan Coil Unit associated with the inoperable nonitor collect grab a limit of detection of at least 10 qtivity (beta or gamma) at samples and analyze for gross radioa

' uCi/ gram at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SALEM - UNIT 2 3/4 3-55 Amendment No. 35

=

4 TABLE 3.3-12 (Continued)

TABLE NOTATION q

ACTION 29 - With the number of channels OPERABLE less than required by the Mininum Channels OPERABLE requirement, effluent releases via this pathway rey continue provided.the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

Pump performance curves ney be used to estinate 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 to the tank.

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

Frequency Conditio n 1/ wee'k During nornel operation (all MODES) e-1/ day-During operation with an identified primary to secondary leak on either Salem Ulit.

- I l

5 l

l SALEM - UNIT 2 3/4 3-56 Amendment N0. 35 l

a

9

+

HIIS PME INTENTICNAILY BIANK i

Amendment No. 35 SAI2M - INIT 2 3/4 11-16 f

m

TABLE 4.11-2 (Continued)

TABLE NOTATION a.

The LLD is defined in Table 4.11.1 b.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be datected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported.

c.

Sarpling and analysis shall also be perforced following shutdown, startup or a THERMAL POWER change that, within one hour, exceeds 15 percent of RATED THERMAL POWER unless:

a 1.

Analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased mare than a factor of three.

e.

2.

The noble gas activity monitor shows that effluent activity has not increased. by more than a factor of three.

s.

d.

Tritium grab sarples shall.be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

e.

Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f.

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance'with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

9

, SALEM - UNIT 1 3/4 11-10 Anendnent No. 64

TABLE 4.11-2 (Continued)

TABLE NOTATION g.

Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after removal from sampler).

Sampling shall also be perforned at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change that, within one hour, exceeds 15 percent of RATED THERMAL POWER and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 124 hours0.00144 days 0.0344 hours 2.050265e-4 weeks 4.7182e-5 months are analyzed, the corresponding LLDs may be increased by a factor of

10. This requirenent does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the prinary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of three.

l 1

SALEM - UNIT 1 3/4 11-11 Amendment No. 64

.-_w

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volure.

APPLICABILITY: At all times.

ACTION:

a.

With the concentration of oxygen in the waste gas holdup system' greater than 2% by volune but less than or equal 4% by volune, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the waste gas holdup system greater than 4% by volume immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volume without delay.

3-c.

The provision of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitor required OPERABLE by Table 3.3-13.

If hydrogen is not measured, the concentration of hydrogen shall be assumed to exceed 4% by volume.

I I

SALEM - UNIT 1 3/4 11 15 Anendment No. 64 i

I b

RADI0 ACTIVE EFFLUENTS BASES 3/4.11.2.5 EXPLOSIVE GAS MI)TURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup systen is reintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

t-3/4.11.3 SOLID RADI0 ACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, ' ut are not c

limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

l l

SALEM. UNIT 1 B 3/4 11 6 Amendment ~No. 64 l

l

It 6-

~

s TABLE 3.3-12 RADI0ACTI_VE LIQJID EFFLUENT MONITORING INSTRUMENTATION w

MINIMUM CHANNELS INSTRUMENT

~

OPERABl.E_

ACTION 1.

GROSS RADIDACTIVITY MONITORS PROVIDIMG AUTOMATIC TERMINATION OF RELEASE Liquid Radwaste Effluent Line (2-R18) 1 26 a.

b.

Steam Generator Blowdown Line 4

27 (2-R19 A, B, C, and D) 2.

GROSS RADI0 ACTIVITY MONITORS NOT PROVIDING AUTOMATIC w1 TERMINATION OF RELEASE di a.

Containment Fan Coolers - Service Water Line 3

28 (2-R13 A, B C) Discharge b.

Chemical Waste Basin Line (R37) 1 31 3.

FLOW RATE MEASUREMENT DEVICES a.

Liquid Radwaste Effluent Line 1

29 p

b.

Steam Generator Blowdown Line 4

29 k

44 TANK LEVEL INDICATING DEVICES a.

Temporary Outside Storage Tanks as Required 1

30 M

TABLE 4.11-2 (Continued)

TABLE NOTATION a.

The LLD is defined in Table 4.11.1 b.

The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:

Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks that are reasurable and identifiable, together with the above nuclides, shall also be identified and reported.

c.

Sampling and analysis shall also be performed following shutdown, startup or a THERMAL POWER change that, within one hour, exceeds 15 percent of RATED THERMAL POWER unless:

1.

Analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of three.

The noble gas activity monitor shows that effluent activity has not

~

2.

increased by more than a factor of three.

d.

Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when the refueling canal is flooded.

e.

Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area whenever spent fuel is in the spent fuel pool.

f.- The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation i

made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3.

L 1

SALEM - UNIT 2 3/4 11-10 Anendment No. 36 l

F

TABLE 4.11-2 (Continued)

TABLE NOTATION g.

Samples shall be changed at least once per 7 days and analyses shall be corpleted within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing (or after renaval from sampler).

Sarpling shall also be perforned at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup or THERMAL POWER change that, within one hour, exceeds 15 percent of RATED THERMAL POWER and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of

10. This requirerent does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the primary coolant has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased by more than a factor of three.

a

. i. -

e-SALEM - UNIT 2 3/4 11-11 Amendment No. 36

RADI0 ACTIVE EFFLUENTS O

EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.5 The concentration of oxygen in the waste gas holdup system shall be limited to less than or equal to 2% by volune.

APPLICABILITY: At all times.

ACTION:

a.

With the corcentration of oxygen in the waste gas holdup system greater than 2% by volune but less than or equal 4% by volune, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the waste gas holdup system greater than 4% by volume immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 2% by volune without delay.

e-c.

The provision of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations of hydrogen and oxygen in the waste gas holdup system shall be determined to be within the above limits by continuously monitoring the waste gases in the waste gas holdup system with the oxygen monitor required OPERABLE by Table 3.3-13.

If hydrogen is not ceasured, the concentration of hydrogen shall be assumed to exceed 4% by volune.

l l

I l

l l

SALEM - UNIT 2 3/4 11-15 Anendnent No. 36 l

i

~

RADI0 ACTIVE EFFLUENTS 9k BASES 3/4.11.2.5 EXPLOSIVE GAS MI)TURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas holdup system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in i

conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50.

g.

3/4.11.3 SOLID RADIOACTIVE WASTE This specification implements the requirements of 10 CFR Part 50.36a and General.

Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM r.ay include, but are not limited to waste type, waste pH, waste / liquid / solidification agent / catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

SALEM - UNIT 2 B 3/4 11-6 Amendment No. 36

.

ML20128K446

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