ML19309B112

ASME Code Equipment & Related Insps & Testing.

ML19309B112
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/25/1980
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML19309B107	List: ML19309B106 ML19309B108 ML19309B109 ML19309B110 ML19309B111 ML19309B112
References
P-80064, PROC-800325, NUDOCS 8004030136
Download: ML19309B112 (9)

Text

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Enclosure 5 ,

to P-80064 i

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~ FORT ST. VRAIN INSERVICE INSPECTION AND TESTING PROGRAM ASME CODE EQUIPMENT AND RELATED INSPECTIONS AND TESTING 8004080/3 6 '

1. INTRODUCTION During a meeting between the Nuclear Regulatory Commission and Public Service Company of Colorado, held in Bethesda on August 20, 1979, the NRC inquired as to what other inspections and testing were performed at the Fort St. Vrain Nuclear Generating Station, in addition to that currently required by the plant Technical Specifications. The purpose of this enclosure is to respond to the NRC inquiry as related in paragraph 1.5 of Reference 1 which states:

"No systems related to reactor safety were evidently built to ASME Code. Those portions of the plant which were built to ASME Code are inspected under the provisions of Section VIII. At the August 20 meeting, PSC agreed to provide a list of equipment in this category.

PSC will also identify inspections and testing for safety related equipment that is not now currently included in the Technical Specifications."

The following is a brief discussion in response to the two questions raised in the above NRC inquiry:

2. FORT ST. VRAIN EQUIPMENT BUILT TO ASME CODES A variety of Fort St. Vrain equipment was designed and fabricated to AS!E code requirements. As pointed out in the NRC comment, no Fort St. Vrain systems were fabricated to ASME code requirements. Fort St.

Vrain equipment items, both safety-related and nonsafety-related, which were built to AS4E code requirements are identified in the attached list.

Fort St. Vrain ASME code equipment was built to the requirements of either Section III or Section VIII. Generally, components of the PCRV reactor coolant boundary were built to Code Section III, Class A; pressure retaining components of the PCRV secondary containment were built to Code Section III, Class B; other pressure retaining components which may contain appreciable amounts of radioactivity were built to Code Section III, Class C; the remaining pressure retaining components were built to Code Section VIII. In all cases, the applicab e edition l

of the ASME Boiler and Pressure Vessel Code is the 1965 Edition as amended by all issued addenda up to and including the Winter 1936 Addenda.

3. INSPECTION UNDER PROVISIONS OF THE ASME CODE As previously stated in several meetings between NRC and PSC,Section XI Division 2 of the ASME Code, which is still in a draf t form and not officially published, was not in effect when the Fort St. Vrain Nuclear Generating Station was designed and constructed. Therefore, no inspections are currently performed under the provisions of this Section of the ASME Code.

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1 Inspections which currently fall under the provisions of the ASf1E Code are those perfonned after equipment items, originally designed and fabricated under the provisions of the Code, have been repaired or modified. ASME Code inspections are performed to the extent that the repairs or modifications are required to be inspected under the provisions of the AStiE Code applicable to the original design and fabrication process. Such inspections are not expected to be performed on a regular basis. For specific equipment items which may never have to be repaired or modified, ASME code inspections would never be required or performed.

4. THIRD PARTY INSPECTIONS fiumerous third party inspections have been carried out in a consistent manner for many years at the Fort St. Vrain Nuclear Generating Station.

The two major inspection agencies involved are the Hartford Steam Boiler Inspection and Insurance Company, and the American fluclear Insurers both of which have sent inspectors to the site who have performed inspections in areas not currently covered by the plant Technical Specifications.

American Nuclear Insurers inspectors primarily concentrate in the areas of fire protection, storage of combustibles, housekeeping, and hydraulic oil system leakage.

Inspectors of Hartford Steam Boiler Inspection and Insurance Company are involved in the review of repair procedures, inspection of repairs, and testing of equipment. Typical equipment has included the steam generator, the auxiliary boiler, the main turbine generator, the boiler feedpumps, the main condenser, and pressure retaining vessels built to the ASME Code, not all of the equipment involved being safety related.

Hartford personnel are notified when major repairs or modifications are necessary. Recent examples of their involvement include inspections and review of repair procedures associated with the steam generator module B1-1 tube repair, testing of the new auxiliary boiler, and repair of pressure vessel T-2105. PSC is also in receipt of and follows up on bulletins published by ANI.

Operational inspections of the feedwater, condensate, feedwater heater extractions and drains, circulating water, ACM, and the electrical distribution systems have also been performed. General aspects of the refueling shutdown were reviewed by both Hartford and ANI inspectors.

Although the reports of these inspections do not specifically outline the total inspector man-days of effort, PSC records indicate that over the past two years eleven separate inspections were performed which corresponds to greater than 58 man-days on site.

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5. PSC INSPECTIONS AND TESTS PSC regularly conducts a complete spectrum of inspections and tests in conjunction with routine and non-routine plant operations, routine and non-routine plant maintenance activities, and plant modification activities. These inspections and tests are performed in response to a wide variety of requirements and conditions (manufacturer's recommendations, good utility practices, industry (non-ASME) codes and standards, etc.),

and are not centered around whether a particular equipment item is safety related.'

Illustrative of the kinds of inspections and tests performed, in response to these miscellaneous requirements, are the inspections and tests required by PSC's Manual for Safe Practices. This PSC manual requires that all safety and relief valves be inspected on a periodic basis to assure these valves are in good operating condition. Depending on the application of the specific safety or relief valve, proper ketpoint may be checked, proper hand operation may be checked, absence of v lve gags will be confinned, etc. Likewise, the PSC manual requires t t all turbine overspeed safety devices be periodically tested. The actu 1 test methods which may be employed will vary depending on the type of turbine governor being tested.

6. CONCLUSIONS The inspection and testing activities described above enconpass a '

wide range of requirements, purposes, and types of systems and equipment.

PSC has concluded that most of these inspection and testing activities would not be suitable or desirable for inclusion in the Fort St. Vrain Technical Specification Surveillance Requirements, even though safety-related systems and equipment may be involved. PSC has been and will continue to assess these other types of inspections and tests, and will recommend that applicable ones of these inspections and tests be included in the inservice inspection and testing program, as appropriate.

7. REFERENCES Reference 1: NRC meeting minutes of August 20, 1979, Docket No. 50-267 I (G-79189 dated October 20,1979)

ISI'COMMfTMENT-LISTOFPLANTEQUIPMENTBUILTTOASMECODE

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j ASME SAFETY CODE COMMENTS P&I DRAWIN EQUIP. # DESCRIPTION 8 RELATED SECTION c_39n7 Decay Removal Heat Exchanger VIII 42-1 T-4201 Service Water Return Sump ASME Code Concrete 42-1 F-4601 Coolina Water Yes III-C F-4602 Fil ter Yes III-C

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A-4601 Cooling Water Yes III-C A 4602 Demineralizer Yes III-C T-4601 Surge Yes VIII T-4602 Tanks Yes VIII E-4601 Cooling Yes VIII TEMA Class R 46-2

_E-4602 Water Yes VIII 46-2 E-4603 Heat Yes VIII TEMA Class R 46-2 l

E-4604 .Fxchanaers l A,lB.lC,l D Yes VIII TEMA Class R 46-2 E 4701 Purification Coolino Yes VIII TEMA Class R 47 E-4702 .Water Exchangers Yes VIII TEMA Class R 47 T-4701 Purification Cooling Water Yes VIII 47 l T-4702 Expansion Tanks Yes VIII 47 T-5201 Bypass Flash Tank VIII 52 F-6201 Liquid Waste III-C 62 F-620lS Filters III-C 62 T-6202 Liquid Waste 62 T-5203 Receivers VIII 62

,T-6204 Liouid Waste Monitor Tank VIII 62 l A-6201 Liquid Waste III-C 62 A-620lS Demineralizers III-C 62 T-6301 Gas Waste Vacuum Tank VIII 63-1 T-6302 Liouid Drain Tank VIII 63-1 T-6303 Gas Waste III-C 63-2 T-6304 Surce Tanks III-C 63-2 T-7303 Low Temperature not Water dystem cvnancinn Tank VIII 73-3 T-7305X Water Chiller Bldo Air Receiver VIII 73-8 T-7506X Evaporative Cooler Bldg Air Receiver VIII 75-7 T-82r 4x Instrument Air Compressor Unioader Yes VIII 82-1 I Receiver l l l

, T o?n? corviro Air Receiver VIII 82-1 M-9104Y HVdraulic Yes VIII-Div. 1 91-2 i M oln6v Oil Yes VIII-Div. I 91-2

ISICOMMITMENT-LISTOFPLAqTEQUIPMENTBUILTT0.ASMECODE. Page 2

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SAFETY ASME CODE COMMENTS P&I EQUIP. 8 DESCRIPIT0N *#

RELATED SECTION M 010RX Accumulators Yes VIII-Div. 1 91-2 M-9110X ll .Yes VIII-Div. 1 91-2 M-9112X through Yce V! Div. 1 91-2 M-9114X lP Yes VIII-Div.1 91-2 M-9116X "

Yes VIII-Div.1 91-2 M-9118X Yes VIII- Div. 1 91-2 Y-915fX ' HyUra'ul'ic 'dil Backup ,

VIII 91-3

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T-9'152'X Storage Tank 1C & 10 VIII 91-3 T-9204X Stand-by Generators Yes VIII 92-2 T-9205X 1A & IB Yes

• T-9206X Starting Air Receivers " " I T-9207X 1 A & 1B T-1101 PCRV Safety Valve Tank tes IIIB 11-5 F-1101 PCRV Relief Filter IIIC 11-5 T-2102 Recirculator Yes IIIC 21-3 T-21025 Containment T-2103 Tanks T-21035 1A,lB,1C & ID " " "

E-2102 Buffer Yes VIII 21-3 E-2102S Helium " " "

E-2103 Coolers " "

n E-210: lA & IB " " "

T- 21 '. J Helium Dryer Knockout Pot VIII 21-3 F-2105 Bearing Water Yes VIII 21-4 F-2105S Make-up Filters " " "

T-2104 Bearing Water Yes IIIC 21-4 T-2105 Surge Tank 1A & 1B " " "

F-2104 Emergency Bearing Yes VIII 21-4 F-2104S Water Filters " " "

E-2104 Bearing Yes VIII Tema Class R 21-5 E-2104S Wate.- " " ' "

E-2105 Coolers " " " ' '

E-2105S 1A, 18, 1C & ID ' '

E-2101 Backup Bearing Water VIII Tema Class R zi-b E-2106 Cooler lA & IB " '

F-2101 Bearing Water Yes VIII ti-a F-210lS Filters

15I dDMMITMENT-PLANT EQUlPMENT BUFLT TO ASME CODE Page 3

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SAFETY ASME CODE P&I EOUIP. d DESCRIPTION RELATED SECTION COMMENTS DRWG #

F-2102 1A,lB,1C & 1D Yes VIII 21-5 F-2102S F-2103 Backup Bearing Water VIII L 21-5 F-21'035 Filters l A & IB "

21-5 T-2110 Turbine Water Drain Tank Yes VIII 21-6 T-2111 Low Pressure Separator VIII 21-6

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'T-2117 Helium Recovery Compressor Knockout Drom VIII 21-6

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T-2118 " " " " " " "

T-2112 Gas Pressurizer Yes VIII 21-7 T-2114 Bearing Water Accumulator Yes VIII 21-7

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T-2121-1 Backup Bearing Yes VIII 21-7 T-2121-2 Water " " "

T-2121-3 Accumulators " " "

T-2106 High Pressure Separator lA Yes IIIC 21-7 T-2122-1 Backup Bearing Yes VIII ui-8 T-2122-2 Water " " "

T-2122-3 Accumulators " " "

T-2107 High Pressure Separator 1B Yes IIIC 21-8 T-2113 Gas Pressurizer Yes VIII 21-9 T-2115 Bearing Water Accumulator Yes VIII 21-9 T-2123-1 Backup Bearing Yes VIII 21-9 T-2123-2 Water " " "

T-2123-3 Accumulators "

T-2108 High Pressure Separator 1C Yes IIIC 21-9 T-2124-1 Backup Bearing Yes VIII 21-10 I T-2124-2 Water " "

T-2124-3 Accumulators " '

T-2109 High Pressure Separator ID Yes IIIC 21-10 J-2107 Seal Water VIII 21-13 E-2107S Coolert " "

T-2120 Separator VIII 21-13 i B-2201 Steam Generators Yes IIIA 22-1 T-2201 Steam / Water Dump Talk IIIC Class 2 22-5 ,

B-2202 Steam Generator Yes IIIA 22-6 )

'_T-2202 Pre-Flash Tank VIII 22-10 l T-2203 "

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• IST COMMITMENT-PLANT EOUIPMENT GUILT TO ASME CODE

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SAFETY ASME CODE COMMENTS P&I EQUIP. # DESCRIPTION RELATED SECTION DRWG.

A-2301 High Temperature Yes  : Cooler & Lines Class A Below 23-1 i A-2302 Filter Adsorbers "

III Primary Closure "

E-2301 Helium Purification Coolers Yes He. Side IIIC 23-1 E-2302 Helium Pruification Coolers Yes He. Side IIIC Water Side-VIII 23-1 A-2303 Helium Purification Yes III-C 23-1 A-2304 Dryers "

III-C "

E-2303 Low Temperature Yes III-C 23-1 E-2304 Gas to Gas Exchangers "

,III-C "

i A-2305 Low Temperature Yes III-C 23-1 3 A-2306 Adsorbers " " "

F-2301 Purified Helium Yes III-C 23-2 I F-2302 Filters " " "

l E-2305 Regeneration Cooler

$DhliY 1 23-3 T-2303 Regeneration Compressor Containment Ttnk III-C 23-3 E-2309 Regeneration Compressor Water Cooler Tube-III-C Shell VIII 23-3 T-2301 Regeneration Knockout Drum III-C 23-3 A-2307 Regeneration Dryer III-C 23-3 E-2306 Regeneration Heater III-C 23-3 E-2307 Hydrogen Removal Economizer III-C 23-4 A-2309 Hydrogen Getter III-C 23-4 A-27095 Units " "

F-2304 Hydrocen Removal Filter III-C 23-4 E-2308 Purified Helium Cooler He.sideIII-C water VIII 23-4 T-2403 Surge Tank VIII 24 T-2401 Helium Storage Tanks VIII 24

{2bs(dF3i A-2401 Oil Adsorber VIII 24 T-2402 High Pressure Helium Supply Tanks VIII 24 Case 1205 (SF 3)

T-2503 Moisture Yes VIII 25-1 T-2504 konitor " " "

T-2505 Supply Tanks n ,,

o T 9R06 1 A.18. IC.1D " " "

l T-XO?  ! icuid Nitrocen Surae Tank Yes 25-2 VIII E-1105 H.P. Feedwater 5 VIII 31-1 E- 3106 Heater 6 " "

F 1101 !nw prneenrn ro n 4_s, + n r unatnr viii 1 31 - 3 E-3102 2 i __

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SAFETY ASME CODE P&I EQUIP. # DESCRIPTION RELATED SECTION COMMENTS .DRWG #

E-3103 Low Pressure Feedwater Heater 3 VIII 31-3 E-3104 Deaerating Feedwater Heater 4 VIII 31-3 T-2501 Liquid Nitrogen Storage Tank Yes VIII 25-1 R-1104 Core Barrel Yes VIII R-1101 PCRV-Primary Closures Yes III-A Secondary Closures Yes III-B Core Support FToor Casing Yes III-A

& Columns D-1201 Control Rod Drive Assembly Yes III-A Primary Closure Components S-2101 Helium Dryer Unit III-C 21-3 R-1101 PCRV penetration liners Yes III-A R-1101 PCRV Liner Yes III-A 46-5 W

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