ML20147F448

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Effluent & Waste Disposal Semiannual Rept for Third & Fourth Quarters of 1987
ML20147F448
Person / Time
Site: Yankee Rowe
Issue date: 12/31/1987
From: Papanic G
YANKEE ATOMIC ELECTRIC CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
FYR-88-028, FYR-88-28, NUDOCS 8803070351
Download: ML20147F448 (20)
v • d • e


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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR THIRD AND FOURTH QUARTERS. 1987 Yankee Atomic Electric Company Rowe, Massachusetts 2819R/4.242 8803070351 871231

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TABLE-1A

' Yankee' Atomic Electric Company. Rowe Massachusetts-Effluent and Waste Disposal Semiannual Report g

Third-and Fourth Quarters. 1987 Caseous Effluents - Summation of All Releases Unit Quarter-

. Quarter Est. Total 3

4 Error. 1

'A. Fission and Activation Gases

-1.

Total release-Ci 7.74E+01 7.17E+01 25.50E401 2.-Average release rate for period uCi/sec 9.85E+00 9.12E+00

3. Percent of Tech. Spec. limit (1)(4) %

7.86E-01 8.04E-01 B. Iodines

1. Total Iodine-131 Ci 2.10E-05 4.25E-06 r2.50E+01
2. Average release rate for period uCi/see 2.67E 5.41E-07
3. Percent of Tech. Spec. limit (2)(4) %

1.65E-01 1.09E-01 C. Particulates

1. Particulates with T-1/2 > 8 days Ci 2.69E-06 2.71E-06 m3.00E+01
2. Average release rate for period uCi/sec 3.42E-07 3.45E-07
3. Percent of Tech. Spec. limit 1

(3)

(3)

4. Gross alpha radioactivity Ci 2.80E-08 1.42E-08 D. Tritium
1. Total release Ci 9.42E-01 1.47E+00 23.00E+01
2. Average release rate for period uCi/see 1.20E-01 1.87E-01
3. Percent of Tech. Spec. limit (3)

(3)

[

e (1) Technical Specification 3.11.2.2.a for gamne air dose.

Percent values for Technical Specification 3.11.2.2.b for beta air dose are approximately the same.

(2) Technical Specification 3.11.2.3.a for dose f rom I-131. Tritium, and radionuclides in particulate form.

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(3) Per Technical Specification 3.11.2.3, dose contribution from Tritium and particulates are included with I-131 above in Part B.

(4) The third and fourth quarter percent of Technical Specification limits are based on conservative plant quarterly dose determinations. 2819R/4.242

TABLE IB Yankee Atomic Electric Company. Rowe. Massachusetts Ef fluent and Waste Disposal Semiannual Report Third and Fourth Quarters. 1987 Gaseous Effluents - Elevated Release Continuous Mode Batch Mode (1)

Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4

1. Fission Gases Krypton-85 Ci 2.09E-02 1.36E-02 Krypton-85m Ci 8.68E-01 8.02E-01 Krypton-87 Ci 7.51E-01 8.09E-01 Krypton-88 Ci 1.54E+00 1.58E+00 Xenon-133 Ci 4.06E+01 3.48E+01 Xenon-135 C1 1.52E+01 1.36E+01 Xenon-135m Ci 1.61E+01 1.85E+01 Xenon-138 Ci 4.83E-01 5.26E-01 Xenon-133m Ci 8.68E-01 4.63E-01 Arnon-37 Ci 3.38E-02 2.55E-02 Arnon-41 Ci 4.62E-01 3.35E-01 Carbon-14 Ci 3.60E-03 2.34E-03 Xenon-131m Ci 5.21E-01 2.78E-01 Unidentified Ci Total for period Ci 7.74E+01 7.17E+01
2. Iodines Iodine-131 C1 2.10E-05 4.25E-06 Iodine-133 Ci 1.63E-05

<1.67E-06 Iodine-135 Ci (1.90E-06 (1.92E-07 Total for period Ci 3.73E-05 4.25E-06

3. Particulates Strontium-89 Ci (7.72E-08 (3.79E-08 Strontium-90 Ci (8.69E-09 (5.42E-09 Cesium-134 Ci 9.75E-08 1.04E-07 Cesium-137 Ci 4.05E-07 5.75E-07 Barium-Lanthanum-140 Ci (1.19E-06

<9.54E-07 Zine-65 Ci (9.30E-07 (7.19E-07 Cobalt-58 Ci

<3.97E-07 (2.98E-07 Cobalt-60 Ci 2.06E-06 2.03E-06 Iron-59 Ci (8.27E-07 (6.44E-07 Chromium-51 Ci 8.14E-08 52.04E-06 Zirconium-Niobium-95 Ci 1.99E-08

<5.05E-07 Cerium-141 Ci (3.41E-07

<2.65E-07 Cerium-144 Ci

<1.47E-06 (1.14E-06 Antimony-124 Ci

<3.71E-07 (2.96E-07 Manaanese-54 Ci 2.40E-08

<3.13E-07 Silver-110m Ci (3.71E-07 (2.78E-07 Molybdenum-99 Ci

<2.80E-06

<2.13E-06 Ruthenium-103 Ci (3.41E-07 (2.66E-07 Total for period Ci 2.69E-06 2.71E-06 (1) There were no batch mode releases during this reporting period. 2819R/4.242

-TABLE 10 "7

Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters 1987 Gaseous Effluents - Ground Level Releases There were no routine measured ground level continuous or batch mode gaseous releases during the third or fourth quarters of 1987.

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0 TABLE 2A

. Yankee Atomic Electric Company. Rowe. Massachusetts Ef fluent and Waste Disposal Semiannual Report Third and Fourth Quarters. 1987 Liquid Effluents - Summation of All Releases Unit Quarter Quarter Est. Total 3

4 Error. %

A. Fission and Activation Products

1. Total release _(not including tritium. mases, alpha)

Ci

4. 29E-03 1.29E-03 22.00E+01
2. Average diluted concentration durina period uCi/ml 6.76E-11 2.00E-11
3. Percent of applicable limit (1) 7.18E-03 1.41E-03 B. Tritium
1. Total release Ci 3.12E+01 5.48E+01 el.00E+01
2. Average diluted concentration durina period uCi/ml 4.91E-07 8.50E-07
3. Percent of applicable limit (1) 1.64E-02 2.83E-02 C. Dissolved and Entrained Gases
1. Total release Ci
1. 9 7E-02
7. 5 7E-02 22.00E+01
2. Average diluted concentration during period uCi/ml 3.10E-10 1.17E-09
3. Percent of applicable limit (2) 1.55E-04 5.85E-04 D. Gross Alpha Radioactivity
1. Total release Ci (2.66E-06

<3.41E-06 23.50E+01 E. Volume of waste released (prior to dilution) liters 7.28E+06 6.44E+06 23.00E+01 F. Volume of dilution water used durina period liters 6.35E+10 6.45E+10 25.00E+00 I

(1) Concentration limits specified in 10CFR, Part 20, Appendix B. Table II, Column 2 (Technical Specification 3.11.1.1).

The percent of applicable limit reported is based on the average diluted concentration during the l

period. At no time did any relesse exceed the concentration limit.

(2) Concentration limits for dissolved and entrained noble gases is 2E-04 microcuries/ml (Technical Specification 3.11.1).

The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concentration limit.

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TABLE 2B Yankee Atomic Electric Company. Rowe. Massachusetts

. Ef fluent and Weste Disposal Semiannual Report Third and Fourth Quarters. 1987 Liquid Effluents Continuous Mode-Batch Mode Nuclides Released Unit Quarter Quarter Quarter Quarter 3

4 3

4 Strontium-89 Ci (1.98E-04

<2.39E-04 2.58E-05

<1.37E-06 Strontium-90 Ci 2.02E-07 (2.99E-05 6.36E-06 1.40E-06 Cesium-134 Ci 2.49E-05 6.23E-06 5.44E-04 6.16E-05 Cesium-137 Ci 1.02E-04 1.53E-05 6.71E-04 9.07E-05 Iodine-131 Ci 2.19E-05 1.85E-05 1.25E-03 2.41E-04 i

Cobalt-58 Ci

<3.41E-05 (4.12E-05 3.55E-06 (6.55E-06 Cobalt-60 Ci 3.37E-05 8.55E-06 1.38E-04 4.26E-05 Iron-59 Ci

( 7.10E-05

<9.25E-05 2.22E-06

<1.31E-05 Zine-65 Ci (8.48E-05

<9.91E-05

<2.32E-05 (1.52E-05 Manzanese-54 Ci

<3.73E-05

<4.43E-05 3.17E-05 5.53E-07

-Chromium-51 Ci (2.75E-04

<3.28E-04

<1.40E-04 (7.16E-05 Zirconium-Niobium-95 Ci

<5.98E-05

<7.23E-05 7.51E-07 2.11E-07 Molybdenum-99 Ci (2.71E-04

<3.13E-04 (7.55E-05 (4.67E-05 Technetium-99m Ci 1.27E-05 2.33E-06

<1.67E-05

<1.02E-05 Barium-Lanthanum-140 Ci (1.15E-04

<1.41E-05

<5.00E-05 (2.63E-05 Cerium-141 Ci (4.76E-05 c5.57E-05 (2.67E-05 (1.66E-05 Ruthenium-103 Ci (3.31E-05

<4.18E-05 (1.45E-05 (7.76E-06 Cerium-144 Ci

<2.18E-04

<2.50E-04

<1.24E-04 3.57E-06 i

Iodine-133 Ci

<3.57E-05

<4.09E-05 1.82E-04 2.37E-05 Selenitam-75 Ci

<3.88E-05 (4.59E-05

<2.08E-05

<1.09E-05 Silver-110m Ci (3.56E-05 (4.10E-05

<1.22E-05 (7.53E-06 Antimony-124 Ci

<3.52E-05 (4.12E-05

<1.66E-05 2.84E-06 8.09E-04 8.21E-04 Carbon-14 Ci Iron-55 Ci

< 6. 71 E-0 3

<5.98E-03 4.25E-04

<4.56E-04 Cesium-136 Ci

<3.46E-05 (4.34E-05

<1.00E-05 (6.77E-06 Unidentified Ci j

i Total for period (above) Ci 1.95E-04 5.09E-05 4.09E-03 1.29E-03

~ Xenon-133 Ci

<9.63E-05

<1.19E-04 1.09E-02 6.32E-02 Xenon-135 Ci (4.72E-05

<3.29E-05 1.18E-04 7.56E-05 Xenon-131m Ci

<1.20E-03

<1.44E-03 6.95E-05 1.93E-03 l

Xenon-133m Ci

<2.42E-04 (2.84E-04 1.10E-04 2.63E-04 Krypton-85 Ci (1,12E-02 (1.37E-02 8.49E-03 1.02E-02 1 2819R/4.242

TABLE 3 Yankee Atomic Electric Company 2,Rowe Massachusetts Effluent and Waste Disposal Semiannual Report Third and Fourth Quarters. 1987 Solid Waste and Irradiated Fuel Shipments c

r A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)*

Unit 6-Month Est. Total L

Period Error. % _,

1. Type of Waste 3

8.10E+00

a. Spent resins, filter sludges, evaporator m

bottoms, etc. - LSA container **,+

Ci 7.93E-01 23.00E+01

b. Dry compressible waste, contaminated m3 1.61E+02 equipment, etc. - 1SA container ++

Ci 4.04E+00 1.00E+02

[_

c. Irradiated componer.ts, control rods, mJ IJ etc.

Ci 3

L d.

m Ci m3 e.

Ci

2. Estimate of Major Nuclide Composition (By Type of Waste)***

b-a.

Hydrogen-3

% 3.51E+01 b.

Cesium-137

% 3.24E+01 E-Cesium-137

% 2.26E+01 Cesium-134

% 2.97E+01 Eg Cesium-134

% 1.92E+01 Iron-55,

% 2.65E+01 E-Iron-55

% 1.74E+01 Cobalt-60

% 3.94E+00 1

Cobalt-60

% 2.67E+00 Niobium-95

% 2.66E+00 Nickel-63 1 1.44E+00 Nickel-63

% 2.06E+00 Iron-59

% 1.57E+00 5

Manganese-54 % 1.10E+00

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3. Solid Waste Disposition ff Number of Shipments Mede of Transportation Destination 6

Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None.

+ Container volume equal to 55 gallons (drums).

++ Container volume equal to 105 ft3 (boxes).

    • Solidification agent is cement.
      • Excluding nuclides with half-lives less than 12.8 days.

-- 2819R/4.242 r

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APPENDIX A Radioactive Liquid Effluent Monitorina Instrumentation Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.6.

With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specification 3.3.6.b requires an explanation for the delay in corracting the inoperability in the next Semiannual Effluent Release Report.

Response

The flow rate measuring device for the steam generator blowdown tank effluent (Table 3.3-8) which was installed during the last reporting period was calibrated and declared operational on t

November 19, 1987. ACTION Statement 17 of Table 3.3-8 way still in effect, until the flow rate measuring device for the steam generator blowdown tank effluent was calibrated.

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APPENDIX B Radioactive Gaseous Effluent Monitorina Instrumentation Requirement: Radioactive gascous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.7.

With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specification 3.3.3.7.b requires an explanation ior the delay in correcting the inoperability in the next Semiannual Effluent Release Report.

I Responset Since the requirements of Technical Specification 3.3.3.7 governing the operability of radioactive gaseous ef fluent monitoring instrumentation were met for this reporting period, no response is required.

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APPENDIX C Liquid Holdup Tanks Requirement: Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any outside temporary tank.

With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification 3.11.1.4, a description of the events leading to this condition is required in the next Sealannual Ef fluent Release Report.

Response

The limits of Technical Specification 3.11.1.4 were not exceeded during this reporting period.

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2819R/4.242

4 APPENDIX D Radiological Environmental Monitorina Proaram Requirementt The radiological environmental monitoring program is conducted in accordance with Technical Specification 3.4.12.1.

With milk

(

or fresh leafy vegetation samples no longer availeble from one or more of the required sample locations, Technical Specification 3.4.12.1.c requires the identification of the new location (s) for obtaining replacement sample (s) in the next Semiannual Effluent Release Report and inclusion cf revised Off-Site Dose Calculation Manual Figure (s) and Table (s) reflecting the new location (s).

Responset All required milk and fresh leafy vegetation samples were available during this reporting period.

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APPENDIX E Land Use Census Requirement A land use census is conducted in accordance with Technical Specification 3.12.2.

With a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose comitment than the values currently being calculated in Technical Specification 4.11.2.3, Technical Specification 3.12.2.a requires the identification of the new location (s) in the next Semiannual Effluent Release Report.

Response

The land use census for this reporting period did not identify any locations yielding at least a 20 percent greater dose or dose comitment than the values currently being calculated in i

Technical Specification 4.11.2.3.

Requirement: With a land use census identifying a location (s) which yields a calculated dose or dose comitment (via the same exposure pathway) at least 20 percent greater than at a location f rom which sarrples are currently being obtained in accordance with Technical Specification 3.12.1. Technical Specification 3.12.2.b requires that the location (s) be added to the program if permission from the owner to collect samples can be obtained and if sufficient sample volume is available. The identification of the new location (s) is required in the next Semiannual Effluent Release Report.

Response

No changes were made in the Radiological Environmental Monitoring Program as a result of the 1987 land use census.

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2819R/4.242 1

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APPENDIX F 1

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?rocess Control Fronram Requirement: Technical Specification 6.14.1 requires that licensee initiated i

changes to the Process Control Program be submitted to the Commission in the Semiannual Radioactive Effluent Release Report' for the period in which the change (s) was made.

Responset There was no licensee initiated change (s) to the Process control Program during this reporting period.

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APPENDIX G Off-Site Dose Calculation Manual Requirecent: Technical Specification 6.15.2 requires that licensee initiated changes to the Off-Site Dose Calculation Manual be submitted to the Commission in the Sealannual Radioactive Effluent Release I

Report for the period in which the change (s) was made effective.

Response

There were no licenaee-initiated changes to the Off-Site Dose Calculation Manual during this reporting period.

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APPENDIX X Radioactive Liquid. Gaseous, and Solid Waste Treatment Systems l

Require: ment: Technical Specification 6.16.1 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semitanual Radioactive Effluent Release Report for the period in which the evaleation was reviewed by the Plant Operation Review Committee.

Response

There were no licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) during this reporting period.

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u APPENDIX I Supplemental Information Third and Fourth Quarters. 1987 1.-

Technical Speelfication Limits - Dose and Dose Rate Technical Specification and Category Limit a.

Noble Gases 3.11.2.1 Total body dose rate 500 mres/yr 3.11.2.1 Skin dose rate 3000 mren/yr 3.11.2.2 Gamma air dose 5 mrad in a quarter 3.11.2.2 Camma air dose 10 mrad in a year 3.11.2.2 Beta air dose 10 mrad in a quarter 3.11.2.2 Beta air dose 20 mrad in a year b.

Iodine-131. Tritiam and Radionuclides in Particulate Fora With Half-Lives Greater than 8 days 3.11.2.1 Organ dose rate 1500 mres/yr 3.11.2.3 Organ dose 7.5 mrem in a quarter 3.11.2.3 Organ dose 15 area in a year c.

Liquids 3.11.1.2 Total body dose 1.5 mrem in a quarter

~

3.11.1.2 Total body dose 3 mres in a year 3.11.1.2 Organ dose 5 area in a quarter 3.11.1.2 Organ dose 10 mrem in a year 1

1-1 2819R/4.242 i

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2.

Techtical Specification Limits - Concentration 1

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Technical Specification and Category Limit h

a.

Noble Gases No MPC limits w

b.

Iodine-131. Tritium and Radionuclides No MPC limits E

in Particulate Form With Half-Lives Greater then 8 days P

L k

c.

Liquids

[

3.11.1.1 Total sum of the fraction of MPC j

(10CFR20 Appendix B. Tables II, Column 2), excluding noble gases less than:

1.0 I

3.11.1.1' Total noble gas concentration 2E-04 uCi/cc h k.r-)

c a 3.

Measurements and Approximations of Total Radioactivity 3j &

l)

.j $ M ?

a.

Noble Cases

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"Continuous discharges" are determined by indirect measurement.

^

L Primary gas samples are taken periodically and analyzed.

It is BIR RMRH r

assumed that in primary to secondary leakage all gases are ejected IBRIidiRGEij through the air ejector.

In primary coolant charging pump leakage all gases are ejected to the primary vent stack either during b

flashing or liquid waste processing. "Batch discharges" are determined by direct measurement. Errors associated with these measurements are estimated to be !55 percent.

h b.

Icdines s

T Iodines are continuously monitored by drawing a sample from tne primary vent stack through a particulate filter and charcoal E

cartridge. The filter and charcoal cartridge are removed and

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I-2 2819R/4.242

1 analyzed weekly. The errors associated with these measurements are l

estimated to be 125 percent.

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c.

Particulates The particulate filter described in (b) above is anal;; red weekly.

The errors associated with the determination of particulate effluents are estimated

, be 30 percent.

d.

Liquid fffluents Liquid effluents are determined by direct measurement.

In line composite samples are analyzed for strontium-89, strontium-90, gross alpha activity and carbon-14. There is no compositing of samples for tritium or dissoPred fission gas analysis. For continuous discharges composite samples are used for gamma isotopic analysis. A gamma isotopic anclysis is performed on a representative sample for each batch release using the Marinelli Beaker geometry. Th3 errors associated with these measurements are as follows:

fission and activation products, 120 percent; tritium.

10 percent; dissolved fission gases, 120 percent; alpha activity, 22.-

-* cent.

4.

Esteh Releases a.

Liquids Third Quarter Number of batch releases:

22 Total time period for batch releases:

9,119 ainutes Maximum tima period for a batch release:

1,975 minutes Average time period for batch releases: 415 minutes Minimum time period for a batch release:

240 minutes Average stream flow during period (Sherman Dam): 437 cfs Average discharge rate:

16.7 gpm I-3 2819R/4.242

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Fourth Quarter Number of batch releases:

18 Total time period for batch releases: 6,371 minutes Maxir 3 time period for a batch release:

1,275 minutes

(

Average time period for batch releases:

354 minutes Minimum time period for a batch release:

240 minutes Average stream L' low during period (Sherman Dam): 836 cfs Average discharge rate:

18.9 gpm b.

Gases There were no batch gaseous releases during the third and fourth quarters of 1987.

f 5.

Abnormal Releases a.

Liquid There were no nonroutine liquid releases during the reporting period.

b.

Gases There were no nonroutine gaseous releases during the reporting period.

I-4 2819R/4.242 I

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TABLE 1A

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Yankee Atomic Electric Company, Rowe, Massachusetts

['. :/

Effluent and Waste Disposal Semiannual Report f 4.: ;.

Thi.-d and Fourth Quarters. 1987

f l' 3 Caseous Effluents - Summation of All Releases

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3.,.,

Unit Quarter Quarter Est. Total 4.L.

3 4

Error, %

k.

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I A. Fission and Activation Gases h

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1. Total release Ci 7.74E+01 7.17E+01 25.50E401

+i ah j.fp w%

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2. Average release rate for period uCi/sec 9.85E+00 9.12E+00

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3. Percent of Tech. Spec. limit (1)(4) %

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... fr - lA x

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B. Iodines a;7.:: -..,

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Ci 2.10E-05 4.25E-06 2.50E+01 i

1. Total Iodine-131
2. Average release rate for period uCi/sec 2.67E-06 5.41E-07 E
3. Percent of Tech. Spec. limit (2)(41 %

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1. Particulates with T-1/2 > 8 days Ci 2.69E-06 2.71E-06 m3.00E+01

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2. Average release rate for period uCi/sec 3.42E-07 3.45E-07 rk p.'['

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3. Percent of Tech. Spec. limit (3)

(3) ib..i a.M

4. Gross alpha radioactivity Ci 2.80E-08 1.42E-08 9,:.lw I

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'0. Tritium

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1. Total release Ci 9.47E-01 1.47E+00 23.00E+01

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2. Average release rate for period uCi/sec 1.20E-01 1.87E-01

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3. Percent of Tech. Spec. limit (3)

(3)

. c.

(1) Technical Specification 3.11.2.2.a for ganr2a air dose.

Percent values for e

Technical Specification 3.11.2.2.b for beta air dose are approximately the same.

b (2) Technical Specification 3.11.2.3.a for dm e from I-131. Tritium, and g

radionuclides in particulate form.

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(3) Per Technical Specification 3.11.2.3, dose contribution from Tritium and

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particulates are included with I-131 above in Part B.

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h (4) The third and fourth quarter percent of Technical Specification limits are

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based on conservative plant quarterly dose determinations.

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Telephone (617) 872-8100 TWX 710-380 7619 1-I V

YANKEE ATOMIC ELECTRIC COMPANY u

a y

1671 Worcester Road, Framingham, Massachusetts 01701 February 26, 1988 FYR 88-29 Uniced States Nuclear Regulatory Commission Attention: Document Control Desk Bashington, DC 20555

Reference:

(a) License No. DPR-3 (Docket No. 50-29)

Subject:

Semiannual Effluent Release Report

Dear Sir:

Enclosed please find the tables summarizing the quantities of radioactive liquid and gaseous effluents aci solid waste released from the Yankee plant at Rowe, Massachusetts for the third a;* fourth quarters of 1987 submitted in accordance with Technical Specification 6.9.5.b.1.

The summary of the estimates of off-site radiation doses resulting from plant effluents during 1987 will be provided in a supplemental report in accordance with Technical Specification 6.9.5.b.2.

We trust that this information is satisfactory; however, should you have any questions, please contact us.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY George apanic, Senior Project Engineer-Licensing GP/25.427 Enclosures cc: USFRC Region I USNRC Resident Inspector YNPS 6 f I

e

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