ML20055G635

Submits Results of Remote Shutdown Panel Environ Survey

ML20055G635
Person / Time
Site:	Comanche Peak
Issue date:	07/17/1990
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-90251, NUDOCS 9007240007
Download: ML20055G635 (4)

Text

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• umummemmen EM F. Log # TXX-90251 C .= File # 10010 4

r C 907 921 RJELECTRIC July 17, 1990 wiin m.t.cohnt.Jr.

Execune Vke brMent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 ,

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50 445 REMOTE SHUTDOWN PANEL ENVIRONMENTAL SURVEY REF: 1) TV Electric letter logged TXX 90029 from William J. Cahill, Jr.

to U._d. NRC, dated January 24, 1990

2) U. S. NRC, " Guidelines for Control Room Design Reviews,"

NUREG 0700, dated September 1981

3) Department of Defense, " Human Engineering Design Criteria for Military Systems, Equipment and Facilities", HIL STD 1472C, dated May 2, 1981

4) CPSES Test Procedure, PPT TP 90A-18. " Hot Shutdown Panel ,

Environmental Survey", dated May 25, 1990 Gentlemen:

Reference 1 submitted Supplement 4 to the CPSES Human Faccors Control Room Design Review Final Report. it reported the status of the final activities of the CPSES Detailed Control Room Design Review (DCRDR) for the licensing of Unit 1, In that reference, it was stated that high temperatures in the remote shutdown area required additional evaluation during power operation. These high temperatures were first identified during an interim remote shutdown environmental survey conducted in the summer of 1984: this was reported as  ;

Human Engineering Discrepancy (HED) No. 354.

In Reference 1, a commitment was made to evaluate this environment during the summer while operating at full power conditions. This commitment was made prior to having a firm schedule for the actual remote shutdown test that was planned during the startup program. After scheduling the remote shutdown test TV Electric determined that this test would provide a more appropriate opportunity for performing the temperature measurements (survey) at the remote shutdown panel because it would require the operators to be stationed C

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TXX 90251 Page 2 of 3 at the panel in accord with actual operating procedures. As a result, it was proposed, after discussion with the NRC Project Manager, to reschedule the temperature survey to occur during the remote shutdown test from about 50%

power. The actual survey measurements were performed on June 5 and 6, 1990, both preceding and following the reactor trip. In this way, the survey measurements included the heat contribution from the rod drive motor-generators (which are located in the immediate area) when they were energized.

Similarly, the measurements also included the heat contribution from the reactor operators themselves once the remote shutdown panel was manned, i

Due to the lack of specific DCRDR guidance provided in Reference 2 on environmental comfort zones for control panels located outside the main control room, the subject was discussed with the NRC staff during the DCRDR 1 audit conducted in January 1989. At that time, it was agreed that Reference 3 i provides suitable guidelines for the acceptablity of personnel enclosures utilized for detail work during extended periods of time. More specifically.

this reference states that the " effective temperature" is to be maintained at or below 850F, where the effective temperature is defined as an arbitrary index which combines into a single value the effect of temperature, humidity >

and air movement on the sensation of warmth or cold felt by the human body.

The numerical value represents the temperature of still, saturated air which would Induce an identical sensation. Reference 4 documented the test equipment and conditions, as well as the data recorded during performance of

'the survey. ,

The survey commenced at 0945 CST on June 5.-1990, with the plant at 49% power.

The reactor was tripped at 0910 CST on June 6 and the remote shutdown was executed. The dry bulb (DB) temperature, relative humidity (RH), air velocity, outside temperature, etc., were all recorded for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to manning the remote shutdown panel and for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following the shutdown. A summary of the test results is provided in the attachment. It is -

to be noted that, throughout the entire period of the measurements, the air velocity was negligible. The HVAC system was in the normal mode of operation during the testing.

By using the nomograph of Reference 3, an effective temperature of 77 to 790F was graphically determined, which averaged 77.80F for the period of the measurements. It is noteworthy that the DB temperature end RH in the remote shutdown area were very stable during the approximately 200F change ,

in outside temperature. Considering the maximum effective temperature for comfort to be 850F. the margin of 7.20F should be adequate to accommodate any foreseeable increase in outside temperature and/or humidity, or additional heat loads in the area.

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TXX-90251 Page 3 of 3 Based on the test results, this HED is considered closed. !f you have any questions, please contact Wendell Knight at (817) 897-8512, or Ray Ashley at (214) 812 8415..

1. Sincerely.

9VJh ,ph* f.

William J. Cahill, Jr.

By: 4f 4 0-1 Roge VD. Walker Manager of Nuclear Licensing -

RLA/vid Attachment c - Mr. R. D. Martin. Region IV Resident Inspectors, CPSES-(3)

J. H. Wilson. NRR i

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REMOTE SHUTDOWN TEMPERATURE SURVEY

SUMMARY

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TEMP HFAC HURMDRY ABIVEt, TERpP REACIOR OtNSEE Clans myrst EFFECTWE 'S[

DATEmME DS

• F ' >  % 2H FPM TERIP ' * ~

WB*P PWR % TERAP *F SPLY *F

--J -- ET

• F 8 4 90/004s e6 43 0 70s 4e '

S2.3 80 - 7e 1346 Sr 43

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70 to 99.9 54 75 174s se 43 4 o se ' es ass' se 7r -

2t4s es 43 se 4e s) ate sa '

77 .l s+santt40 es 43

• o se 4e 7ms as i 77 l os4s er 44 -

ms at us ~ sa as -!

g.

osos or 4s o 7ae 7as oses O e3 65 124s es 44 -

ens 77.s

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• REACTOR TRIF PED 0910 44-90 '

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AVE ET-77.8

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