ML20205T630

Forwards Revised CB-1 Action Plan,Control Room Pressurization Test Results & Summary of Control Bldg HVAC Operation,Per 860609 Telcon Re Control Room Emergency Ventilation

ML20205T630
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/13/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
TAC-61289, NUDOCS 8606160118
Download: ML20205T630 (14)

Text

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- musas a N General M Covigiasiy r - E: firt D WWs Vr e F%% W June 13, 1936 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN: Mr. Steven A. Verga Director PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission Washington DC 20555

REFERENCE:

1) PCE (Withers) to NRC (Varga) Letter Regarding Control Room Emergency Ventilation, June 4, 1986 Control Room Emergency Ventilation System (CB-1)

Pursuant to our conference call with your staff on Monday June 9,1986, a revised CB-1 Action Plan is provided in Attachment 1. This Action Plan formally documents the completion of all items which were identified to be completed prior to startup in Reference 1. Attachment 2 provides the test data which demonstrates the control room can be maintained at 11/8-inch positive pressure. In addition, Attachment 3 provides a brief summary description of the Control Building HVAC under various operating conditions.

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

Sincerely, 8606160118 860613 Bart D. Withers PDR ADOCK 05000344 Vice President P PDR Nuclear Attachments c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Lynn Frank, Director State of Oregon Department of Energy

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O Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 1 of 10 CB-1 ACTION PLAN r Responsible Completion Action Item Basis Engineer Schedule Actions / Comments

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 errors. close this item.

d) Provide supplement PGE May 19, Kershul September 30, 1986 Completion of this item will also con-to Annual Update to 1986 letter firm that dose analysis envelopes all describe most recent postulated accidents.

analyses and design changes.

2) Revise Procedures a) POT 20-1. LER 86-02 Coldmann 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 dampers to be placed in auto-after-open following completion of the tests.

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

TM 86-036 modified makeup damper position status light.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 2 of 10 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments c) POT 20-1. LER 86-02 Coldmann Complete POT 20-1, Rev. 17, requires CB-3&4 to be off during the test.

d) EI-0. LER 86-02 Goldmann 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 Goldmann Complete Heaters set at 70% instead of 100%.

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

setting during the first 10-hr phase of this test during which the capability of CB-1 to maintain the control room <110*F 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 hesters be set at 70% following completion of the test.

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

h) PICT 25-2. May 7, 1986 Bennett Complete Specify <5 ppm, not >5 ppm. l NRC letter i) POT 20-1. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 2, 1986 letter TS 3.7.6.1, Item 8: POT 20-1 will be revised to include acceptance criteria for heater amperage.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 3 of 10 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments j) MP 9-1. PGE May 19 Goldmann 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.

k) PETS 10-1 and 10-2. PCE 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 Complete NRC May 7, 1986 letter, Attachment 3, l

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 Complete NRC May 7, 1986 letter, Attachment 3, l 1986 letter PET 10-1 Item 15: Include TS references.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 4 of 10 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments r) PET 10-3. PGE May 19, Goldmann Complete NRC May 7, 1986 letter, Attachment 3, 1986 letter PET 10-1, Item 16: Correct l typographical errors, s) PET 10-1. PGE May 19, Goldmann December 31, 1986 NRC May 7, 1986 letter, Attachment 3, 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 consisteni.

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. PCE May 19, Goldmann Complete NRC May 7, 1986 letter, Attachment 1, l 1986 letter ONI-54: Revise to specify securing CB-5&10.

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 13, 1986 License NPF-1 Attachment 1 Page 5 of 10 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. Charcoal installed ing at 30*C and in the 1986 refueling outage meets removal efficiency Regulatory Guide 1.52, Table 2 test of >95%. criteria for 2-in. beds located outside Containment. New charcoal will be procured to meet Regulatory Guide 1.52.

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, Kerchul September 30, 1986 NRC May 7, 1986 letter, Attachment 2, time for C1 2. 1986 letter TS 3.3.3.6, Item 2.

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.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 6 of 10 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule ,

Actions / Comments

6) Design evaluation LER 86-02 Kershul Complete Bechtel has performed the design evalu-of CB-3&4. ation. Recommendations include a direct trip of CB-3&4 fans. Procedure changes have been completed to verify CB-3&4 are off on CB-1 initiation.

7) Evaluate toxic gas LER 86-02 Kershul Complete Bechtel has performed the evaluation and protection for CB-1 recommends that CB-1 makeup dampers be when performing closed during POT 20-1. Although toxic POT 20-1. gas detection (Cl 2 ) exists with CB-2 isolated, CB-1 makeup dampers do not automatically isolate. Procedures 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 Complete Evaluation has been completed to deter- l equipment. mine that the instrumentation design tem-perature range is 110*F or greater.

c) Perform temperature PCE June 13, Davis December 31, 1986 ----

survey inside control 1986. letter room cabinets.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 l Page 7 of 10 t

CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments d) Evaluate a replace- Memo ANR- Davis December 31, 1986 ment program for 174-86M aged and heat sensitive control room equipment.

9) Operator check-outs on Internal Kershul Complete ONI-54 requires operator to confica air SCBAs. flow to the face mask. Chemistry Techs have portable devices for detecting toxic gas outside the control room and are trained in their use.

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 Coldmann Complete and PCC 86-536 have been issued to test. resolve Item a). PCC 86-535 has been issued to resolve Item b).

d) Periodically evaluate Internal Rupe 1987 Refueling the ability of CD-1 Outage to maintain a posi-tive pressure in the control room.

Tr@jan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 8 of 10 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments

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 December 31, 1986 Existing procedures are being used on opening penetrations JWL-88-86M on an interim basis. A new A0 will into control room be prepared as a permanent control.

envelope.

13) Flow measurement Inspection Rupe Complete T. Y. Chen (Bechtel) assisted in (

disparities. Report 86-06 completing this task.

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

of chiller for CB-1,

15) Control room heat load Internal Rupe Complete Control room temperature measurements and data. service water inlet and outlet tempera-ture were provided to Bechtel.

16) Evaluate leakage Internal Rupe Complete CB-2 dampers (DM-10501 and -10504) have characteristics of been refurbished. DM-10501 and -10504 dampers isolating are isolation dampers, not low leakago control room dampers. During smoke testing of these envelope from dampers, negligible leakage was observed.

non-safety-related NVAC systems.

17) Submit revised PGE June 9 Walt September 30, 1986 Dose analysis has been completed, other NUREG-0737, III.D.3.4, 1986 letter aspects underway.

control room habitabil-ity submittal.

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Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 9 of 10 CB-1 ACTION FLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments

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

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

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

20) Evaluate design change PGE May 19 Puntenney Complete NRC May 7, 1986 letter Item A.1.g.

and/or TS change regard- 1986 letter This evaluation is the basis for ing CB-1 flow rate. completing Item 4.f in this Action Plan.

21) besign changes:

a) Relocation of CB-1 PGE May 19, Seibel Complete NRC May 7, 1986 letter, Item A.1.1.

l outside air intake. 1986 letter b) Evaluation of instal- PGE May 19, Seibel December 31, 1986 NRC 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 NRC May 7, 1986 letter, Item A.1.J.

1986 letter Evaluated satisfactorily. Dampers meet credible single failure.

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

means to increase air 1986 letter flow rate.

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 1 Page 10 of 10 CB-1 ACTION PLAN Responsible Completion Action Item Basis Engineer Schedule Actions / Comments e) Evaluate automatically PGE May 19, Cooksey Complete NRC May 7, 1986 letter, Items B.2 l stopping CB-5 and 1986 letter and B.4. WSO-172-86 dated May 15, 1986, CB-10. WSO to RLS/JWL.

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.

l GAZ/kal 0830W.686

Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 2 Page 1 of 1 CONTROL ROOM PRESSURIZATION TEST RESULTS CB-1A CB-1B Outside Air Makeup 498 cfm 471 cfm Total Flow 3037 cfm 2986 cfm Positive Pressure to 0.14 to 0.17 in. 0.17 to 0.20 in.

Adjacent Spaces of water of water a

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Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 3 Page 1 of 2

SUMMARY

OF CONTROL BUILDINC HVAC OPERATION Safety Injection Upon receipt of an SI signal, the CB-2 recire and makeup fans are automatically stopped and the CB-2 outside air damper is automatically closed. The CB-1 fans automatically start and the CB-1 outside air dampers automatically open. In addition, CB-3, -4, -5, -6, and -10 are automatically stopped.

High Radiation Upon receipt of a high radiation signal, the CB-2 recire and makeup fans are automatically stopped, and the CB-2 outside air damper is auto-matically closed. CB-1 can be manually started and the CB-1 outside air dampers manually opened per ONI-12. In addition, CB-3, -4, -5, -6, and

-10 are automatically stopped.

Toxic Cas Upon receipt of a toxic gas signal, the CB-2 makeup fan is automatically stopped, the CB-2 outside air damper is automatically closed, and CB-3 and -4 are automatically stopped. CB-2 recire fan is manually stopped, and CB-1 is manually started with the CB-1 outside air makeup dampers maintained closed per ONI-54. In addition, CB-5, -6, and -10 are manually stopped when the CB-2 recire fan is manually stopped per ONI-54.

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Trojan Nuclear Plant Mr. Steven A. Varga Docket 50-344 June 13, 1986 License NPF-1 Attachment 3 Page 2 of 2 CONTROL ROOM HVAC OPERATION CB-2 CB-2 CB CB-1 CB-1 CB-5,6 Recirc M/U 3&4 Fans M/U CB-10 Closed (2)

Normal Operations ON ON ON OFF Red Flagged ON SIS OFF OFF OFF ON Open OFF High Radiation Auto OFF OFF OFF OFF Closed (2) OFF Red Flagged Manual (1) OFF OFF OFF ON Open OFF Toxic Cas Auto ON OFF OFF OFF Closed (2) ON Red Flagged Manual (1) OFF OFF OFF ON Closed OFF POT-20-1 Test OFF OFF OFF ON Closed OFF Carbon Dry ON ON ON ON Closed ON (1) Manual actions are actions required by ONI-12 or ONI-54.

(2) Damper is normally closed (green light) with control switch red flagged.

This allows damper to auto open when CB-1 automatically starts.