ML20093A126
| ML20093A126 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 06/29/1984 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8407100132 | |
| Download: ML20093A126 (5) | |
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P 0. Box 5000 - CLEVELAND, oHlo 44101 - TELEPHONE (216) 622-9800 - lLLUMINATING BLDG.
- 55 PUBLICSOUARE Serving The Best f.ocation in the Nation MURRAY R. EDELMAN VICE PRESIDENT NUCLEAR June 29, 1984 PY-CEI/NRR-0121 L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555 Perry Nuclear Power Plant, Units 1 & 2 Docket Nos. 50-440; 50-441 Control Room Ventilation Testing
Dear Mr. Youngblood:
This letter is provided to reflect a revision in the method of pre-operational testing of the Control Room Heating, Ventilating, Air Conditioning (HVAC) and the Emergency Recirculation Systems at the Perry Nuclear Power Plant.
The proposed change was discussed with your staff in a conference call on June 7, 1984.
The FSAR Section 14.2.12.1.25 presently describes a positive pressurization test for both the normal and emergency operating modes of the control room HVAC systems.
We plan to conduct two pre-operational tests to verify the systems ability to perform within design specifications. A pressurization test will be performed on the control room HVAC system in its normal operating mode and a tracer gas dilution test will be conducted on the emergency recirculation mode of the system.
The use of the tracer gas dilutien method for testing is consistent with the actual HVAC system design, as described in the Section 9.4.1 of the FSAR.
Since the design does not provide for a positive pressure in the control room envelope during emergency conditions but switches to a recirculation mode, testing under positive pressure conditions is not representative of system performance.
Use of a tracer gas and concentration time related measurements provides the ability to test the system in its designed emergency operating mode.
The testing will be conducted in accordance with ASTM E 741-83,
" Measuring Air Leakage Rate by the Tracer Dilution Method".
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t' Mr. B. J.-Youngblood June 29, 1984 s
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To reflect-this revised testing approach, attached are draft FSAR changes to t
Section 14.2.12.1.25 and Table 1.8-1.
These revised pages will be incorporated j
in a future amendment to the FSAR. If you have any question, please contact us.
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t ery truly yours Murr3ay4fAlw,J
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Edelman Vice President I
I Nuclear Group MRE:nje l
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- . Jay Silberg, Esq John Stefano J. Grobe
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.D. Becker
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Prerequisites l
s 1.
Individual component tests have been completed and are approved.
t 2.
Permanently installed instrumentation is properly installed, calibrated i
and operable.
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3.
Instrument air is available.
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4.
Appropriate a-c and d-c power sources are available.
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5.
Test instrumentati'on is available and properly calibrated.
6.
The following systems are operational:
f (a) Control Complex Chilled Water System (b) Adequate fire protection is available (c) Emergency Closed Cooling System (d) Battery Room Exhaust System i
l (e) Standby Diesel Generator System l
t (f) Nuclear Closed Cooling System c.
Test Procedure 1.
Control Room HVAC l
(a) Verify fan, damper and air conditioner interlocks, trips, permissives and control functions.
(b) Verify system will be automatically deactivated by emer-gency signals.
l 14.2-61 L
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(c) Verify that the control room is maintained at a positive pressure with respect to surrounding areas.
(d)
Verify operation times for isolation dampers.
(e) Verify system response to manual isolation and automatic isolation signals.
2.
Emergency Recirculation (a) Verify fan, heater, damper and air handler interlocks, trips permissives and control function.
(b) Verify system will be automatically activated by emergency signals.
(c)
Verify that the control room envelope inleakage criteria is not exceeded.
(d) Verify system response to manual isolation and automatic isolation signals.
(e) Verify HEPA filters and charcoal absorber beds perform to meet the requirements of Section 6.5.1.4.2.
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Acceptance Criteria T~
1.
Fan, heater, damper and air conditioner interlocks, trips, permissives and controls function within design specifications.
2.
Systems respond to emergency signals automatically in accordance with
' design specifications.
3.
a.
Control room is maintained 'at a positive pressure with respect to surrounding areas in accordance with design specifications (Normal Operations).
b.
Inleakage criteria of the control room envelope is not ex-ceeded (Emergency Recirculation).
4.
Operating times for isolation dampers are within design spec-ifications.
5.
System isolation response is within design specifications limits.
6.
HEPA filters and charcoal beds function within design specification N.
c limits.
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TABLE 1.8-1 (Continued)
Regulatory Guide (Rev.;RRRC Category)
Degree of Conformance
-Reference 1.90 - (Revision 1 - 8/77;RRRC Cat. 1)
Inservice inspection of prestressed Not applicable to PNPP design.
concrete containment structures with grouted tendons 1.91 - (Revision 1 - 2/78;RRRC Cat. 2)
Evaluations of explosions postulated to PNPP conforms to this guide.
2.2.3 occur on transportation routes nesc nuclear power plants 1.92 - (Revision 1 - 2/76;RRRC Cat. 1)
Combining modal responses and spatial PNPP design conforms to.this guide.
3.7.3 6
components in seismic response analysis h*
1.93 - (Revision 0 - 12/74;RRRC Cat. 4)
Availability of electric power sources The requirements of Regulatory G'uide 1.93 for 16.3/4.8 Limiting Conditions for Operations are addressed in Technical Specifications.
1.94 - (Revision 1 - 4/76;RRRC Cat. 1)
Quality assurance requirements for PNPP conforms to this guide to the extent 17.2 installation, inspection, and testing of required by ANSI N18.7-1976 structural concrete and structural steel during the construction phase of nuclear power plants 1.95 - (Revision 1 - 2/77;RRRC Cat. 1)
Protection of nuclear power plant control PNPP design conforms to this guide.with exception of 2.2.3 room operators against an accidental item C.S.
Control room leakage shall be determined by chlorine release tracer gas method per ASTM E741-83.
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