ML19351F504

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Tech Specs LCO 4.3.10,Table 4.3.10-1 & SR 5.5.3 for Class I Hydraulic Snubbers & Reactor Exhaust Sys
ML19351F504
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 12/31/1980
From:
PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19351F503 List:
References
NUDOCS 8101130374
Download: ML19351F504 (9)


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ATTAC10fENT 1 PROPOSED CHANGE TO LCO 4.3.10. TABLE 4.3.10-1 AND REASON FOR CHANGE t

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. T S 6 j\\ @JU6uSmu "AI:.I 4. 3.10-1 (een:i=uedl C: ASS I E!DRAr!IC SNUB 3IES (continued) .

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3eiler Teed Scubbers Generaters 325-31-4 375-32-1 375-32-4 375-31-1 375-32-5 375-31-2 375-31-5 375-32-2 373-31-6 375-32-3 375-32-6 375-Il- 3 3eiler 7eed Snubbers 375-526 375-377 375-54 375-421 325-528 375-614 375-138 . 375-422 375-425 375-529 375-641 375-139 375-679 3M-142 375-434-1 375-530 575-532 375-711 373-149 3'75-434-2 375-434-3 3?S-334 375-763 375-152 375-764 175-153 375-435 375-536 3I3-537 375-796 375-297 375-437 375-451 375-553-1 375-820 375-352 375-323 375-397 375-477 375-553-2 375-479 323-556 375-524 375-398 375-843 375-400 375-498 373-563 375-500 375-564 375-844 375-402 375-870 3?S-412 373-501 373-566 315-516 375-572 375-871 375-416 BFS-166 375-420 375-523 375-573 3ciler 7eed Snubbers '-artene-375-89I 375-21?I 3?S-399I 373-14I 3?S-405I 375-15I 375-122I 375-22BI 375-141I 373- 229I 375-414I 3?S-16I 375-417I 375-26I 375-142I 3?S-243I 375-143I 3?S-244I 375-419I 3?S-29I 375-421 375-30I 375-15EI 3PS-245I 375-167I 375-257I 375-422I i'

' 375-31I 375-423I 375-47I 375-181I 375-26CI 375-1973 375-263I 375-430I 375-53I 375-431I 375-56I 375-203I 3?S-264I 375-204I 375-265I 375-432I 373-57I 375-442I 375-74I 375-210E , 375-269I 375-216I 375-444I 375-76I HFSr154I 375-77I 3?S-21SI 375-39 EI

REASON FOR CHA' IGE Audit program for 21/2" and larger piping has identified BFS-166 and BFS-154E, which are located on Class I piping as defined by SR 6-1, but not included in Table 4.3.10-1. Snubbers were apparently omitted f rom the list of Class I snubbers due to an oversight on the part of personnel who per-formed the initial analysis of piping supports. This change corrects that error and fulfills the requirements of LCO 4.3.10(e).

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ATTACIDfENT 2 PROPOSED CHANGE TO SR 5.5.3a)

AND BASIS AND REASON FOR CHANGE I

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

Fort St. Vrain #1 Technical Specifications Amendment Page 5.5-3 Basis for Soecification SR 5.5.2 The reactor building pressure relief device is designed to protect the building in the evcnt that pressure in the Reactor Building exceeds the turbine building pressure by 3 inches of water. The device consists of louvers installed in a number of individual modules operated by mechanical linkages to pneumatic actuators (see FSAR Section 6.1.3.4). The specified test frequency shall ensure the operability of the reactor building relief system.

Specification SR 5.5.3 - Reactor Building Exhaust Filters, Surveillance The exhaust filters in the reactor building ventilation system shall be tested  ;

as follows:

a) A laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Posit.on d C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, shall be performed af ter each 4400 hours0.0509 days <br />1.222 hours <br />0.00728 weeks <br />0.00167 months <br /> of l

l cperation of the unit, or following painting, fire, or chemical

  • l l release in any ventilation zone co=municating with the unit. The

( results of laboratory carbon sample analysis from the unit shall shew > 90% radioactive = ethyl icdide removed when tested in ac-l cordance with ANSI N510-1975 (130*C, 95% R.H.).

  • Defined as any material which could reasonably be expected to interfere with the charcoal to adsorb methyl iodide.

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Fort St. Vrain #1 Technical Specifications

! Amendment Page 5.5-4 b) A halogenated hydrocarbon test shall be performed once per calendar year or af ter each replacement of a charcoal adsorber bank or af ter structural maintenance on the filter housing. Halogenated hydro-carbon removal by the charcoal filters shall be > 99% when conducted at normal flow conditions in accordance with the applicable portions of ANSI N510-1975.

c) The HEPA filters shall be leak tested in place once per calendar year, af ter each complete or partial replacement of a HEPA filter bank, or af ter any structural =aintenance on the filter housing, using cold DOP. Cold DOP removal by the HEPA filters shall be

?. 99% when tested in accordance with the applicable portions of ANSI N510-1975.

d) Flow distribution across the HEPA and charcoal filters will be tested with initial operation of the system and following any struc-cural modification to the filter housings. Air distribution shall be demonstrated within i 20% across the HEPA and charcoal filters I

when tested in accordance with ANSI N510-1973.

i e) Total pressure drop across the combined HEPA filter and charcoal adsorber banks shall be less than 6" 2H O at filter design flow

+ 10%.

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Fort St. Vrain >?1 Technical Specifications Amendment

Page 5.5-5 Basis for Specification SR 5.5.3 The reactor building exhaust filter system is designed to filter the reactor building atmosphere prior to release to the facility vent stack during both nor=al and accident conditions of operation. The system consists of three 50% capacity units, two of whien are in continuous operation, with the third on standby.

i High efficiency particulate air (HEPA) filters are installed before the char-i J

coal adsorbers to remove particulate matter froE the air stream to prevent

! clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential release of radiciodine to the at=osphere. Bypass leakage for the charcoal adsorbers and particulate removal efficiency for HEPA fil-ters are determined by halogenated hydrocarbon and DOP respectively. The i

i laboratory carbon sa=ple test results indicate a radioactive methyl iodide recoval efficiency for expected accident conditions. The surveillance test I frequencies specified establishes system performance capabilities. If system conditions are specified, the calculated doses will be less than the guide-lines stated in 10 CFR 100 for the accidents analyzed, as indicated in Sec-

! tions 14.S and 14.12 of the FS AR. Pressure drop across the combined HEPA fil-I ter and charcoal adsorber of less than 6 inches of water at the filter de-l sign ficw rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign =atter.

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Fort Se. Vrain #1 Technical Specifications Amendment Page 5.5-6 The activated carbon adsorber in the affected unit should be replaced if a representative sample f ails to pass the iodine removal efficiency test. Any HEPA filters found defective should be replaced.

If painting, fire, or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated f rom the fumes, chemicals, or f oreign materials, the same tests and sample analysis should be performed, as required, for operational surveillance.

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l REASON FOR CHANGE I

i Public Service Company Change Notice No. 868 added external carbon sample canisters across the charcoal adsorbers in the reactor building ventilation system exhaust filters to allow periodic sampling of charcoal effectiveness

without affecting the integrity of the adsorber beds.

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, This change reflects the NRC staff practice described in Regulatory Guide 1.52, j Revision 2, March 1978.

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