ML20079B249

Proposed Changes to Part a of ODCM

ML20079B249
Person / Time
Site:	Seabrook
Issue date:	12/27/1994
From:	NORTH ATLANTIC ENERGY SERVICE CORP. (NAESCO)
To:
Shared Package
ML20079B245	List: ML20079B242 ML20079B249
References
PROC-941227, NUDOCS 9501050354
Download: ML20079B249 (6)

Text

J 1

2 . 0, RESPONSIBILITIES FOR PART A All changes to Part A of the ODCH shall be reviewed and approved by the Station Operation Review Committee (SORC) and the Nuclear Regulatory l Commission prior to implementation.

It shall be the responsibility of the Station Manager to ensure that the ODCH is used in the performance of the surveillance requirements and administrative controls of the appropriate portions of the Technical Specifications.

A.2-1 9501050354 941227 PDR ADOCK 05000443 p PDR

TABLE A.3-1 , . ,

Radioactive Liauld Waste Samolina and Analysis Procram -

i (continued) 1 Minimum Lower Limit of.

Sampling Analysis Type of Activity Detection (LLD) 'F 1 Liquid Release Type Frequency Frequency Analysis .(I) (uct/ml) .

H-3 1x10'5 y

• M Grab Sample Gross Alpha 1x10'7 -

W 9' S "9 5x10 8 t

Grab Sample 0 (9) s Steam Generator Pr.incipal Gamma 5x10 7 C.

> Blowdown Flash W Emitters c33

'u* Tank (6ns) Grab Sample 1x10'8 I-131 w

(Continuous Dissolved and W M Entrained Gases 1x10'S Release)(5) Grab Sample (Gamma Emitters)  ;

H-3 1x10

y M

Grab Sample Gross Alpha 1x10*7 Sr-89, Sr-90 5x10-s- ,

g

' j Grab Sample 0 (9) 1x10

Fe-55 t

i

+

t

_ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ - _ . _ , .. ..w - .~, g.-w-*, y -. , , , _ . -, , , , , , , . ,. , . , , , , _.# , . < . . ..,,...m.- . , , , a._m .%~ ~ , . . . . .m , .., .. , _ , _ _,,m ,

TABLE A.3-1

- Notations -

(Continued)

(3) 'The principal gamma emitters for which the LLD specification applies include the following radionuclides: Hn-54, Fe-59, Co-58, Co 60, Zn-65, Mo 99, Cs-134. Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report in l accordance with Technical Specification 6.8.1.4. Isotopes which are not detected should be reported as "not detected." Values determined to be below detectable levels are not used in dose calculations.

"I A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

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

(6) Sampling and analysis is only required when Steam Generator Blowdown is directed to the discharge transition structure.

U3 Principal gamma emitters shall be analyzed weekly in Service Water. Sample and analysis requirements for dissolved and entrained gases, tritium, gross alpha, strontium 89 and 90, and Iron 55 shall only be required when analysis for principal gamma emitters exceeds the LLD.

The following are additional sampling and analysis requirements:

a. PCCW sampled and analyzed weekly for principal gamma emitters.

b. Sample Service Water System (SWS) daily for principal gamma emitters whenever primary component cooling water (PCCW) activity exceeds 1x10'3 uC/cc.

c. With the PCCW System radiation monitor inoperable, sample PCCW and SWS daily for principal gamma emitters.

d. With a confirmed PCCW/SWS leak and PCCW activity in excess of 1x10" uC/cc, sample SWS every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for principal gamma emitters.

e. The setpoint on the PCCW head tank liquid rate-of-change alarm will be set to ensure that its sensitivity to detect a PCCW/SWS leak is equal to or greater than that of an SWS radiation monitor. located in the unit's combined SWS discharge, with an LLD of 1x10-8 uC/cc. If this sensitivity cannot be achieved, the SWS will be sampled once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

(8) If the Turbine Building Sump (Steam Generator Blowdown Flash Tank) isolate due to high concentration of radioactivity, that liquid stream will be sampled and analyzed for Iodine-131 and principal gamma emitters prior to release.

l A.3-6

I P

TABLE A.3-1 1

' Nota ti ons '

(Continued)

.' j - m Quarterly composite analysis requirements shall only be required when '

l analysis for principal gamma emitters indicate positive radioactivity. 6 i

i f

i h

e o

b l

A.3-7

l TABLE A.4-1 .

Radioactive Gaseous Waste Samoling and Analysis Program (continued) l Minimum Lower Limit pf Sampling Analysis Type of Activity Detection'3 Gaseous Release Type Frequency Frequency Analysis (LLD) (uCi/cc)

3. Gland Steam W Principa)2) Gamma Packing Continuous Particulate Emitters 1x10'll Exhauster Sample Continuous Charcoa Sample Ix10*

H Gross Alpha 1x10'll Continuous PM'%e Sample

- 0 Sr-89, Sr-90 Continuous 1x10'll

$ Pfrb ake Sample (8) l

4. Containment p(3) Principal2) Gamma 1x10

Purge Each Purge Grab Each Purge Sample H-3 (oxide) 1x10

f !

i^ #

, ,il TABLE A.4-1

- Notations (Continued) l (2) The principal gamma emitters for which the LLD specifications applies include the following radionuclides: Kr-87. Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59 Co-58, Co-60 Zn-65, Mo-99, 1-131, Cs-134 Cs-137, Ce-141 and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radioactive Effluent Release Report in accordance with l Technical Specification 6.8.1.4. Isotopes which are not detected may be reported as "not detected." Values determined to be below detectable levels are not used in dose calculations.

m Sampling and analysis shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one hour period unless: 1) analysis shows that the DOSE EQUIVALENT I-131 concentrations in the primary coolant has not increased more than a factor of 3: 2) the noble gas activity monitor for the plant vent has not increased by more than a factor of 3. For containment purge, requirements apply only when purge is in operation.

W Tritium grab samples shall be taken 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 refueling canal is flooded.

m 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 Technical Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

W Samples shall be changed at least once per seven (7) days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler. Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least seven (7) days following each shutdown, startup, or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER within a one-hour period and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing, When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if: 1) analysis shows that the DOSE EQUIVALENT I-131 concentration in the reactor coolant has not increased more than a factor of 3: and 2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

m Samples shall be taken prior to start-up of condenser air removal system when there have been indications of a primary to secondary leak.

(8) Quarterly composite analysis requirements shall only be required when l analysis for principal gamma emitters indicate positive radioactivity. l A.4-5

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