ML20195F006

Forwards Revised Dose Calculation Analysis & Schedule for Completion of Control Room Emergency Ventilation Sys & Revised CB-1 Action Plan,Per 860528 Request

ML20195F006
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/04/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
TAC-61289, NUDOCS 8606090324
Download: ML20195F006 (15)

Text

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em W Getier'ai M CorTixuiy E Bad D Wmers Vce Presdent June 4, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor-Regulation ATTN: Mr. Steven A. Varga Director PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission .

Washington DC 20555

Dear Sir:

Control Room Emergency Ventilation System (CB-1)

Pursuant to our meetings with you and members of your staff, Wednesday, May 28, 1986, a copy of our revised dose calculation and a schedule for completion of the activities involving the subject system were requested.

Attachment 1 to this letter is a revised copy of the dose analysis of the control room emergency ventilation system. Please note that the maximum makeup air flow rate is 525 cfm. Attachment 2 to this letter is a revised copy of our CB-1 Action Plan, showing the varicus action items, completion schedule, and various comments as well as other information for the items and activities to be performed on CB-1.

Should you have any further questions or comments on this matter, please do not hesitate to contact me.

Sincerely, W2 -- ,

Bart D. Withers Vice President Nuclear Attachments c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Lynn Frank, Director l State of Oregon l Department of Energy l n 1 ADO) 8606090324 860604 PDR ADOCK 050003 4 f F l l l 1215w sdmon strent. Pound o<egon 97204

Trojcn Nucisse Pltnt Mr. Stsven A. Vcrgs Docket 50-344 June 4, 1986 License NPF-1 Attachment 1 Page 1 of 5 TROJAN NUCLEAR PLANT RADIOLOGICAL DOSES TO CONTROL ROOM PERSONNEL

I. Introduction:

This calculation determines the maximum filtered makeup flow rate that would be permissible with the control room emergency ventilation intake relocated to the northwest corner of the Control Building roof.

The calculation is based upon the formalism and equations provided by Murphy and Campe in " Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19", CONF-740807, 13th AEC Air Cleaning Conference. Provided in the following sections are the data used as the input parameters for the Murphy-Campe equations for determining the inhalation thyroid, ganna whole body, and beta skin doses. The radionuclide source terms from both Containment and recirculation leakage are presented.

The calculation shows that NRC limits for control room doses will be met with filtered makeup flow rates of 525 cfm or less.

II. X/Q Parameter:

I A. The x/Q was calculated using the diffuse source-point receptor equation from Murphy-Campe. The air intake for the control room  !

i ventilation (CB-1) was moved to the northwest corner of the Control Building roof.

I

1. The following presents the values of parameters used for calculating the x/Q

a. Distance between Containment surface and receptor = s = 145 ft = 44.20 m.

b. Diameter of Containment = d = 131 ft = 39.93 m (UFSAR Section 3.8.1.1.1).

i

c. Mean wind speed (corresponding to 5 percent meteorology) =

u = 1.13 m/sec (UFSAR, Section 2.3.4).

d. Cross-sectional Containment area = a = 2340 m -(UFSAR 2

-Section 2.3.4).

2. Gaussian diffusion parameters were determined from Figures A.2 and A.3 of Meteorolony and Atomic Enermy 1968 by extrapolation for a receptor distance of 145 ft.

ay = 2.8 m az = 0.90 m i

}

Trojtn Nuclear Plcnt Mr. Stsven A. Vergs 1

Docket 50-344 June 4, 1986 4

License NPF-1 Attachment 1 Page 2 of 5

! 3. Therefore x/Q = 1.71 x 10-3 sec/m3 at 145 ft. .

4. As presented in Table 1 of Murphy-Campe, the value of x/Q was decreased for the Table 1 stated time intervals by the changes in wind speed and direction.

1 j B. The recirculation leakage x/Q is the same as that for Containment leakage because of the elevation difference between the release j point (top of Containment for Auxiliary Building vent) and emergency ventilation intake (roof of Control Building)

(Murphy-Campe).

1 III. Dose Conversion Factors:

A. Thyroid inhalation:

1. Breathing rate = 3.47 x 10-4 m3 /sec (Nurphy-Campe).

i ,

i 2. Iodine radionuclide dose conversion factors from UFSAR j Table 15.0-8 or ICRP Committee II Report (1959).

4 B. Whole body and skin:

i Dose conversion factors from Regulatory Guide 1.109 Table B-1.

I V'. Iodine Protection Factors (IPF):

j A. Equation 11 of Murphy-Campe, with the parameter values of:

F1 = Filtered makeup air = 525 cfm F2 = Filtered recirculation air = 3000 cfm -Fi j F3 = Unfiltered air infiltration = 10 cfm (Murphy-Campe) n = Filter efficiency = 0.95 for organic and elemental (Regulatory Guide 1.52) l

= 0.99 for particulate.

B. Therefore, for:

I 1. Elemental and organic radiolodines: IPF = 79.62.

2. Particulate radiolodines: IPF = 195.75.

V. Miscellaneous Factors:

A. Purge factor (PFj):

1

! The Trojan control room is not considered to be tight or isolated j so purge factors for each time interval are taken as one.

t 4

-=-c y ~----__,r. , - . - , - , - . . . . . . , - ,v'm--- --w a-m-,- v - , * = = - +-e+-+v=*rv-- +-ev-v**ww*-= v

Trojan Nucl0Cr Plint Mr. Stcvin A. V:rg3 Docket 50-344 June 4, 1986 License NPF-1 Attachment 1 Page 3 of 5 B. Geometry factor (GF):

1. GF = 1173/VO .338 [ Equation (9) of Murphy-Campe].

where V = control room volume in ft3 = 81,300 ft3 (UFSAR Section 6.4.4.1.2)

2. Therefore, GF = 25.7.

C. Occupancy factors:

From Murphy-Campe, Table 1, for the different time intervals.

VI. Radionuclide Releases During Time Intervals:

A. Containment:

1. Radionuclide source term was calculated using the core activity release model described in UFSAR Section 15.6.5.6.1.

2. The following table presents the radionuclide source terms for Containment for the Murphy-Campe time intervals.

CURIES RELEASED FROM CONTAINMENT Period 1 Period 2 Period 3 Period 4 Period 5 Nuclide (0-2 hr) (2-8 hr) (8-24 hr) (24-96 hr) (96-720 hr)

Kr-83m 9.63E+02 7.76E+02 9.24E+01 1.18E-01 2.57E-13 Kr-85 8.33E+01 2.50E+02 6.65E+02 1.50E+03 1.28E+04 Kr-85m 2.82E+03 4.65E+03 2.71E+03 1.17E+02 1.34E-03 Kr-87 3.85E+03 1.86E+03 7.27E+01 5.74E-03 4.51E-20 Kr-88 7.10E+03 8.55E+03 2.45E+03 2.36E+01 4.14E-07 Kr-89 4.49E+02 2.29E-09 3.06E-43 0.0 0.0 Xe-131m 5.55E+01 1.65E+02 4.28E+02 8.65E+02 3.49E+03 Xe-133 1.68E+04 4.94E+04 1.24E+05 2.20E+05 4.39E+05 Xe-133m 4.25E 12 1.21E+03 2.81E+03 3.71E+03 2.45E&O3 Xe-135 4.29E&O3 9.60E+03 1.18E+04 2.51E+03 1.11E+01 Xe-135m 8.48E+02 4.09E+00 4.51E-07 6.30E-26 0.0 Xe-138 3.02E+03 2.27E+01 9.36E-06 4.42E-23 0.0 I-131 2.29E+02 3.75E+02 9.61E+02 1.85E+03 5.57E+03 I-132 2.92E+02 1.47E+02 2.87E+01 1.17E-01 4.53E-11 I-133 5.03E+02 7.27E+02 1.36E+03 8.86E+02 9.07E+01 I-134 3.99E+02 4.18E+01 3.47E-01 4.79E-07 4.62E-32 I-135 4.37E+02 4.72E+02 4.45E+02 5.30E+01 3.19E-02 I

. -- - - - - _ . . . . . - . -. . ._ _-.. . -- .-- - = .

. L j Trojan Nucisse Plant Mr. Stcven A. Varga

! Docket 50-344 June 4, 1986 I License NPF-1 Attachment 1

' Page 4 of 5 l

4, ,

l B. Recirculation leakage:

1 1. Radionuclides from recirculation leakage undergo a depressuri-I zation and are waterborne to the Auxiliary Building so the noble gas releases are insignificant when compared to containment noble gas releases. Therefore, only radioiodines will be considered in the source term for recirculation

! leakage. These radioiodines will be assumed to be elemental l

and/or organic in chemical species.

1 2. The methodology used for recirculation leakage determination f

will be from EUREG-75/087-1979, Chapter 15.6.5, Appendix B.

1

3. Fifty percent of the reactor core radiolodines are assumed to be in containment sump which has a volume of the primary i coolant system (12,250 ft3), plus the Refueling Water Storage

- Tank (46,900 ft 3),

4. The radiolodine activities in Containment sump at the time of i recirculation pump starting (0.867 he after accident) are given in Table 15.6-14 of UFSAR.

5. The radiciodine activities released during a given time period were calculated using Equation 15.6-5 of the UFSAR. The terms

! of Equation 15.6-5 are defined in UFSAR Section 15.6.5.6.1 of i UFSAR with the leakage rate, L, taken as twice the value defined in this section (from NUREG-75/087-1979).

i 6. For the radioiodine releases from the Auxiliary Building, an i iodine-wster partition factor of 0.1 was assumed for deter-i mining tt.e amount of radiolodine available for release (UFSAR j Section 15.6.5.6.1).

! 7. The following table presents the radiolodine source term

! activities with the respective time interval.

i I Recirculation Leakane Source Ters (C1) '

4 Nuclide 0.867-8 hr 8-24 hr 24-96 hr 96-720 hr 1 1-131 6.48E+1 1.39E+2 5.38E+2 1.63E+3 I-132 3.16E+1 4.15E+0 3.39E-2 0 I-133 1.27E+2 1.96E+2 2.56E+2 2.62E+1 I-134 1.51E+1 5.05E-2 0 0

I-135 8.64E+1 6.45E+1 1.53E+1 9.24E-3 VII. Containment Shine and External Cloud Shine Doses

! The samma whole body doses from containment shine and external cloud i shine are presented in Table 15.6-17 of the UFSAR. However, these

' doses were determined with a control room occupancy factor one third of j that defined in Murphy-Campe (Table 1), so the doses in Table 15.6-17

-+--me,, myw-+-y~e-m-+r..e+v*,e-9-em-- .=-a, --==-emgm--vip-*-e- -

'++yc +-e-*T-*ir-ei

Trojan Nuciccr Picnt Mr. Stcven A. V rgs Docket 50-344 June 4, 1986 License NPF-1 Attachment 1 Page 5 of 5 of the UFSAR were multiplied by a factor of three and added to the Murphy-Campe calculated doses.

VIII. Sunmary of determined control room personnel doses for the emergency ventilation makeup intake on the northwest corner of control Building roof and makeup flow rate of 525 cfm.

Doses Camma Thyroid Whole Body Beta Skin Inhalation Source (rem) (rem) (rem)

Internal cloud 0.93 13.1 29.8 Containment Shine 0.24 - -

External Cloud 0.003 - -

Total 1.17 13.1 29.8 4

l

.s i NCD/kal 0924W.686

. -- - - - .. ... _- - -- _ - _ - . . _ _ _ - ~ . . _ . _ ___- - - .- .. -_ _

Trojan Nuclear Plant Mr. Steven is. Varga Docket 50-344 June 4, 1986 License NPF-1 Attachment 2 Page 1 of 9 CB-1 ACTION PLAN i

Responsible Completion Action Item Basis Engineer Schedule Actions / Comments .

t j 1) Correct FSAR a) Section 12.3.3.2.3 LER 86-02 Kershul July 1, 1986 LDCR 86-07 (Annual FSAR Update) will to require makeup air close this item.

damper open.

b) Figure 9.4-3 to LER 86-02 Kershul July 1, 1986 LDCR 86-07 (Annual FSAR Update) will

' specify a heater close this item.

setting of 70%.

c) Misc. cross-reference LER 86-02 Kershul July 1, 1986 LDCR 86-07 (Annual FSAR Update) will i errors. close this item.

2) Revise Procedures

[) POT 20-1. LER,86-02 Goldmann Complete POT 20-1, Rev. 17, requires the dampers to be closed during the test.

b) POT 20-1. LER 86-02 Goldmann Complete Outside air makeup dampers open during LOCA. POT 20-1, Rev. 17, requires the j dampers to be placed in auto-after-open

! following completion of the tests.

} OI 10-2, Rev. 7, requires the dampers to l be in auto-after-open. EI-0 requires j operators to check SI status lights.

TM 86-036 modified makeup damper position status light, i

i c) POT 20-1. LER 86-02 Goldmann Complete POT 20-1, Rev. 17, requires CB-3&4 to be ,

off during the test.

4 i

Trejan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License NPF-1 Attachment 2 Page 2 of 9 CB-1 ACTION PLAN Responsible Completion Action Item Basis Enstineer Schedule Actions /Connents d) EI-0. LER 86-02

• Coldmann Complete CB-3&4 off during LOCA. EI-0 deviated (D86-030) to require that CB-3&4 be verified off by local observation. "

e) POT 20-1. LER 86-02 Coldmann Complete Heaters set at 70% instead of 100%.

POT 20-1, Rev. 17, specifics a 70%

setting during the first 10-he phase of this test during which the capability of CB-1 to maintain the control room 1110*F e is confirmed. POT 20-1, Rev. 17, specifies a 20% setting during the second 10-hr phase of this test when the charcoal filters are dried.

f) POT 20-1. LER 86-02 Goldmann Complete Heaters set at 70% during LOCA.

POT 20-1, Rev. 17, requires the heaters be set at 70% following completion of the test.

g) PET 10-2. Internal Goldmann Prior to startup Correct typos to specify 130*C and 30*C, not 130% and 30%.

h) PICT 25-2. May 7, 1986 Bennett Prior to startup Specify 15 ppm, not >5 ppm.

NRC letter i) New PET. PCE May 19, Goldmann December 31, .986 NRC May 7, 1986 letter, Attachment 2, 1986 letter TS 3.7.6.1, Item 8: Demonstrate heater capability.

j) MP 9-1. PGE May 19, Coldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1 Item 1: Make MP 9-1 consistent with PETS 10-1, 10-2.

D ,

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License NPF-1 Attachment 2 Page 3 of 9 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions /Conunents k) PETS 10-1 and 10-2. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1, Item 3: Require sampling carbon at time of installation.

1) Air flow tests. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1, Item 5: Damper positions for tests.

m) PET 10-4. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986. letter PET 10-1, Item 9: Specify which dampers are open.

n) PET 10-4. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1, Item 11: Check Dampers DM-10251 A&B.

o) PET 10-4. PGE May 19, Goldmann Prior to startup NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1, Item 13: Check closure of inner redundant damper.

p) PET 10-4. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1, Item 14: List all appropriate components.

q) PET 10-4. PGE May 19, Goldmann Prior to startup NRC May 7, 1986 letter, Attachment 3 1986 letter PET 10-1, Item 15: Include TS references.

c) PET 10-3. PGE May 19, Goldmann Prior to startup NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1, Item 16: Correct typographical errors.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License NPF-1 Attachment 2 Page 4 of 9 CB-1 ACTION PLAN Responsible Completion '

Action Item Basis Engineer Schedule Actions / Comments s) PET 10-1. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, a

1986 letter PET 10-1, Items 17 and 18: Revise PET data sheets, t) PICTs 25-1 and 25-2. PGE May 19, Bennett December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter PICT 25-1, Item 2: Make procedures consistent.

i u) ONI-54. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter ONI-54. Items 2 and 3: Starting both emergency fans, damper closure, v) ONI-54. PGE May 19, Goldmann Prior to startup NRC May 7, 1986 letter, Attachment 1, 1986 letter ONI-54: Revise to specify securing CB-5&l0.

w) PICT 25-2. PGE May 19, Bennett December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 1986 letter PICT 25-24, Item 1: Correct editorial errors.

x) ONI-12. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 2, 1986 letter TS 3.7.6.1, Item 5: Provide guidance.

3) Verify line Damper PGE May 19, Goldmann Complete NRC May 7, 1986 letter, Attachment 3, DM-10502 is capped off. 1986 letter PET 10-1, Item 11: Check Dampers DM-10251A&B. Damper DM-10502 was removed, line is capped.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License NPF-1 Attachment 2 Page 5 of 9 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments

4) Evaluate TS Changes.

a) Evaluate TS change to PGE May 19 Kershul September 30, 1986 NRC May 7, 1986 letter, Items A.1.f, require charcoal test- 1986 letter TS 3.7.6.1. Item 2.

ing at 30*C and removal efficiency of 195%.

b) Applicability of NH3 PGE May 19, Kershul September 30, 1986 NRC May 7, 1986 letter, Attachment 2, and SO2 detectors. 1986 letter TS 3.3.3.6, Item 1: Determine operable modes, c) Isolation levels and PGE May 19, Kershul September 30, 1986 NRC May 7, 1986 letter, Attachment 2, time for C1 2. 1986 letter TS 3.3.3.6, Item 2.

1 d) >95% adsorption PCE May 19, Kershul September 30, 1986 NRC May 7, 1986 letter, Attachment 2, efficiency. 1986 letter TS 3.7.6.1, Item 4.

e) Surveillance testing Internal Kershul September 30, 1986 Revise LCA 120.

requirements, f) CB-1 total flow of PGE May 19, Kershul September 30, 1986 NRC May 7, 1986 letter, Attachment 1 3000 cfm. 1986 letter TS 3.7.6.1.

5) Correct Drawing M-239 PGE Puntenney Complete M-239, Rev. 16, issued on April 22, 1986 and any associated April 21, with correct information. No M-500 draw-M-500 series drawing 1986 letter ings identified with discrepancies.

to specify a heater setting of 70% and correct other discrepancies.

. _ . - - - , - . ... - .1 _ , - _ . . . . . .- . .. - - .- _

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License NPF-1 Attachment 2 Page 6 of 9 CB-1 ACTION PLAN Responsible Completion Action Item Basis Enitineer Schedule Actions / Comments

6) Design evaluation LER 86-02 Kershul Prior to startup Bechtel is performing the design of CB-3&4. evaluation. Procedure changes have been completed to verify CB-3&4 are off on CB-1 initiation.

7) Evaluate toxic gas LER 86-02 Kershul Prior to startup Bechtel is performing the evaluation.

protection for CB-1 Although toxic gas detection (C1 2) when performing exists with CB-2 isolated, CB-1 makeup POT 20-1. dampers do not automatically isolate.

Procedares require CB-1 to operate with makeup dampers closed when testing the system. See Item 4)b) above for other toxic gas concerns.

8) Evaluate control room LER 86-02 temperature design basis:

a) 110*F basis. Wehage Complete Bechtel letter dated April 18, 1986.

b) Safety-related Davis Prior to startup Evaluation is in progress to determine equipment. that the instrumentation design tem-perature range is 110*F or greater.

9) Operator check-outs on Internal Goldmann Prior to startup Appears to be complete but still need SCBAs. to verify.

l

o.

Trojan Euclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License EPF-1 Attachment 2 page 7 of 9 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments

10) 1/8" positive pressure Inspection satisfactorily demonstrating a 1/8" posi-in relation to Report 86-06 tive pressure in the control room is the adjacent areas: most important CB-1 related action to be completed this outage. A failure of a) Seal door and Irlandez Complete this test could delay Plant startup.

ceiling leaks. Therefore, sealing of. leaks and per-formance of the test must be done early b) Install permanent Wehage Complete in the outage. This will allow cor-test instrumentation, rective measures to be implemented before scheduled Plant startup in the c) Prepare test event of a test failure. NCR 86-040 procedure / perform Goldmann Prior to startup and PCC 86-536 have been issued to test. resolve Item a). PCC 86-535 nas been issued to resolve Item b).

11) Add instrumentation Inspection Puntenney Complete NCR 86-043 issued to resolve this.

-ports to measure air Report 86-06 flow rates.

12) Administrative control Memo Goldmann Prior to startup The appropriate AO will be revised.

on opening penetrations JWL-88-86M into control room envelope.

13) Flow measurement Inspection Rupe Prior to startup T. Y. Chen (Bechtel) will be assisting

' disparities. Report 86-06 in completing this task.

14) Evaluate feasibility. Internal Wehage September 30, 1986 Bechtel is performing the evaluation.

of chiller for CB-1.

3 a .______ ___ _ _. - - -

l Trojan Euclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License MPF-1 Attachment 2 Page 8 of 9 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments

15) Control room heat load Internal Rupe May 30, 1986 Control room temperature measurements and data, service water inlet and outlet tempera-ture are to be provided to Bechtel.

16) Evaluate leakage Internal Rupe Complete CB-2 dampers (DN-10501 and -10504) have i I

characteristics of been refurbished. DM-10501 and -10504 l dampers isolating are isolation dampers, not low leakage.

! control room dampers.

envelope from l non-safety-related MVAC systems. j i

17) Be-evaluate EUREC-0737, May 7, 1986 Walt Prior to startup Dose analysis has been completed, other

! III.D.3.4, control room ERC letter aspects underway.

l habitability submittal.

18) Permanent fix to drain PGE May 19 -Wehage December 31, 1986 WRC May 7, 1986 letter, Items A.1.a and lines from TE-161A&B. .1986 letter A.1.c.

19) Bevise Plant procedures PCE May.19, Goldmann Complete NRC May 7, 1986 letter, Item A.1.b.

to measure makeup air 1986 letter flow rate every 18 months.

l l 20) Evaluate design change PGE May 19, Puntenney Prior to startup NRC May 7, 1986 letter. Item A.1.g.

and/or TS change regard- 1986 letter ing CB-1 flow rate. .

i ,

l t i - - - . . . -. . . . . , ~ -, - , - - . - . , - . . - . . - . _ - . . - - . - - - -.,,, n - .,

- - . - _ _ - . - - . - - - - . - . .- - .-.- . . - . - - . - -- . _ - - - . - _ . - - . = - - . - . - . ~ _ _ - ._

Trojan Euclear Plant Mr. Steven A. Varga Docket 50-344 June 4, 1986 License EPF-1 Attachment 2 Page 9 of 9 CB-1 ACTION Pt.AN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments

21) Design changes:

a) Relocation of CB-1 PCE May 19, Seibel Prior to startup NRC May 7, 1986 letter, Item A.1.1.

outside air intake. 1986 letter b) Evaluation of instal- PGE May 19 Seibel December 31, 1986 ERC May 7, 1986 letter, Item A.1.1.

lation of charcoal 1986 letter adsorber in makeup ,

line.

c) CB-1 makeup dampers. PGE May 19, Davis Complete ERC May 7, 1986 letter, Item A.1.J.

1986 letter Evaluated satisfactorily.

d) Evaulate permanent PGE May 19, Seibel December 31, 1986 NRC May 7, 1986 letter, Item A.2.a.

means to increase air 1986 letter floor rate.

e) Evaluate automatically PCE May.19, Cooksey Prior to startup NRC May 7, 1986 letter, Items B.2 stopping CB-5 and 1986 letter and B.4. WS0-172-86 dated May 15, 1986, CB-10. WSO to RLS/JW1..

f) Delete CB-1 Internal Seibel December 31, 1986 PGE May 19, 1986 letter, response to preheaters. TS 3.7.6.1, Item 2. Dependent upon test data.

GAZ/kal ,

0830W.686

-.-