ML19345A202
| ML19345A202 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/22/1980 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19338E087 | List: |
| References | |
| NUDOCS 8009240522 | |
| Download: ML19345A202 (165) | |
Text
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=1. TMI RELATED QUESTION ON SECTION II.B.1, REACTOR COOLANT SYSTEM VENTS REQUEST
- a. Provide your design of the pressurizer vent system per our November 9,1979, letter. Assure that all requirements and recommendations of that letter are satisfied.
- b. If a _ break in the vent line is beyond that defined as the smallest LOCA by 10 CFR 50, Appendix A, provide an ECCS performance analysis for a complete spectrum of breaks in the vent line. Assure that the thermal-hydraulic modeling is consistent with break location.
- c. Demonstrate that the exhaust from the vent. system will not impinge on other equipment, that the vent system will vent RCS hot legs, and that the vent exhaust is to a portion of the containment with maximum ventilation and cooling.
- d. Demonstrate that the vent system is qualified to RPS safety grade standards.
Include seismic design, IEEE-279 requirements, minimize inadvertent actuations, vent valve position indication in the control room, qualification to pass non-condensibles, steam, water and combinations, thereof, etc.
- e. Provide procedural guidelines and analytical bases (preferably, generically developed by owners group) for vent operation and termination as related to plant performance. The procedures thould be based on the following criteria:
p (J) the plant must meet the requirements of 10 CFR 50.46 and 10 CFR 50.44 for - DBA's; and (2) the plants ability to maintain core cooling and containment integrity for events beyond DBA's must be increased. Procedures should also address methods to (1) assure natural circulation through the U-tube portions of the steam generator with the potential accumulation of gases in this region, and (2) assure that combustible limits are not exceeded.
RESPONSE
- a. The ability to vent the pressurizer is provided by two installed Power Operated Relief Valves (PORV's) which vent to the pressurizer relief tank. Their associated circuits meet the separation requirements for redundant systems with one PORV Powered from train "A" and the other powered from train "B".
Each PORV is air-operated and equipped with two solenoid-valves in their respective air lines. The solenoids are powered from train A and B 125Vdc buses, respectively. These buses are powered through associated battery chargers which can also be supplied from the train A or B diesel upon' loss of offsite power or from 125Vdc batteries. A system will be installed as a backup system to the instrument air system for operating the~PORV's. Each PORV has a motor-operated block valve located in its respective piping. These valves' associated circuits meet the separation requirements for redundant systems. The operator and its associated control circuits for
-each block valve are. powered from its associated train A or B emergency bus.
A ( !
The motive and control power interfaces (for the PORV's and associated block valves) with the emergency buses are ace.omplished through safety grade devices. These PORV's are operated from the main control room and have positive position indication provided to the operator via stem-mounted limit switches. The PORV's are seismically qualified for static loads. Alabama Power Company is participating in the EPRI Relief and Safety Valve Test Program and will upgrade the PORV's as necessary following the com-pletion of the test program and plant specific analysis,
- b. The Reactor Vessel Head Vent System (RVHVS) is orificed to limit the blowdown from a break or inadvertently opened flow control valve downstream of the orifice to the capacity of one charging pump.
A postulated break of the reactor vessel head vent line upstream of the orifice would result in a small LOCA of not greater than one inch diameter. Similarly, for pressurizer venting using the PORV's a postulated break would result in a small LOCA of approximately 2.5 inches diameter. Such breaks have been analyzed in WCAP-9600, Sections 3.2 and 3.3. This WCAP contains extensive discussions regarding the applicability of the break flow models employed as well as other specific modeling features employed for small break LOCA analysis. The analysis in WCAP-9600 provides ECCS performance analysis and shows that no calculated core uncovery would occur for postulated breaks of sizes corresponding to the RVHVS and PORV vent systems.
- c. The RVHVS will discharge into an open area between the reactor and the CRDM platform. As shown by the attached drawings, this discharge is directed towards the reactor cavity walls and does not impinge on any safety-related equipment. The discharge rate for hydrogen is 5600 ft3 per minute. Dis-charging into the reactor cavity provides sufficient space to prevent any gas collecting. Ventilation is provided by the CRDM cooling fans to ensure optimum dilution of combustible gases.
The exhaust from the pressurizer vent system is directed to the pressurizer relief tank (PRT) which prevents impingement on other safety-related equip-ment. The post-LOCA mixing fans provide ventilation for the entire con-tainment in an accident situation. Three sets of fans will provide sufficient ventilation in case of a PRT disc rupture. For a Westinghouse-designed plant, the RCS hot legs are not a high point in the system. .Therefore venting of the hot legs is not required. j
- d. :The Reactor Vessel Head Vent System ~(RVHVS) provides for venting the reactor !
- vessel and head to remove noncondensible gases or steam using only safety- l grade equipment. The.RVHVS consists of two paralled flow paths with redundant
~
isolation valves in each flow path. A schematic diagram of the RVHVS is shown in Figure 1. Th6 solenoid operated valves in each flow path are powered by opposite vital buses. If one single failure prevents a venting operation through one flow path, the second flow path 'provides a redundant backup. 1
( The two isolation valves in each flow path provide a single failure method of isolating the venting system. Each isolation valve is a fail closed, nonnally closed, active valve. With two valves in series, the failure of any one valve or power supply will not inadvertently open a vent path. Thus, ; the combination of safety-grade train assignments and valve failure modes will not prevent vessel head venting or prevent venting isolation with any single active failure. The RVHVS has two nonnally deenergized valves in series in each flow path. The two series valve arrangements eliminate the possibility of a spuriously opened flow path due to the spurious movement of one valve. As such, power ; lockout to any valve is not considered necessary. The system is operated from the control room. The isolation valves have ! stem position switches which are monitored in the control room by status lights. The RVHVS is seismically designed and supported for seismic, thermal, pressure, deadweight, and dynamic loads resulting from the flow of gases, steam, water, or two-phase flow. The isolation valves will be qualified to IEEE-323-1974, IEEE-382-1972, and meet Regulatory Guide 1.48 (active valves). In addition, this system meets IEEE-279-1971 requirements.
- e. The Westinghouse Owner's Group has approved a program to develop appropriate instruction regarding the conditions under which reactor vessel head vent operations should be conducted, and the manner in which head vent operations would be made. This program is scheduled to be compelted prior to the end
[ of this year so as'to be implemented in plant specific procedures to make the reactor vent systems operational by January 1,1981. It should be noted that the Farley Nuclear Plant already meets the require-ments of 10 CFR 50.46 and 10 CFR 50.44. The addition of the vent systems and its operation will not compromise this ability. The instructions developed as part of the above referenced Westinghouse Owner's Group effort will be developed specifically to enhance the safe recovery of the plant for events beyond the design base to assure that combustible gas limits are not exceeded and also to assure natural circulation through the U-tube portions of the steam generators. The procedural guidelines developed by the Westinghouse Owner's Group will be incorporated into the Farley procedures. 4
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a g L l'J SU,E_STION 122.10: The containment pressure boundary is constructed using materials meeting the requirements of ASME Section III or various B 31.X piping codes; however, our licensing reviews, including that for Farley-2 do not include evaluation of explicit compliance with these codes. Consequently, to complete our final SER for Farley in response to the July 18, 1980 memorandum, D. G. Eisenhut to R. H. Vollmer, we require the following information:
- 1. Identification of the fabrication codes (edition and addenda) and the specific paragraphs in these codes that specify the fracture toughness requirements and acceptance criteria (for weldments and base metals).
Codes and code paragraphs should be identified for all materials which constitute part of the containment pressure boundary (e.g., piping penetrations, personnel airlocks, equipment hatch).
- 2. The materials test data that certify that the fracture toughness acceptance standards have been met for each of the identified materials in the containment pressure boundary.
RE_Sp0NSE:
'O l'.' The Farley-Unit 2 containment penetrations are identified on drawing t
( D-206157 (enclosed). Also enclosed are drawings D-206151, D-206152 and D-207411 which provide detailed information concerning the contain-ment penetrations. A documentation package is enclosed which provides: i (a) a penetration summary that accounts for all penetrations by number and explains which numbers required fracture toughness . tes ts; and,
~
(b) a table of general requirements for containment penetrations which delineates the fabrication codes and other applicable requirements. The table separates penetrations into three categories determined generally by the design specification which governed fabrication. 4
- 2. The enclosed documentation package also includes material test data
> which demonstrates that the fracture toughness acceptance standards required by code have been met for the containment pressure boundary ma terials . All carbon steel penetration materials which serve as containment pressure boundaries, and which exceed 1/2 inch thickness, have been satisfactorily impact tested. ~ Exclusion of carbon steel ! n 1/2 inch thick or less and stainless steel is in conformance with V i
- ASME Section III, Paragraph NE 2300. In the case of forged carbon steel flued heads, successful impact tests were performed for all penetrations .
e __.
s :s 7 to 1: INDEA
- l. Penetration Summary 2.- General. Requirements for Containment Pcnetrations
- 3. Mechanical Penetration Listing ,
Sleeve mill test reports i a.
- b. Cap mill test reports J. '
- c. Flued head mill test reports
- d. Penetration No. ' 84 Equipment Hatch
- e. Code reports
- 1. Penetration #86* Personnel Hatch
{) ! 2. Penetration #87* Auxiliary Hatch , t
- 3. Penetration #84 - Equipment Hatch -
I
- 4. Electrical Penetration Listing 4
- a. Sleeve, cap and adapter mill. test reports I .
r 5. Drawings - j' I 4x )
*MTRs on file at Chicago Bridge and Iron l 1
I 4 I O 2.J----
V O -! I PENETRATION 'JIf tMARY l PENETRATION NUMBERS (Drawing D-206157) COMilENTS I thru 9, 51, 52, 53 Carbon steel flued heads. Material rest Reports attached. , 15 thru 18,-23, 28 ;;'inless steel flued heads. Fracture 56, 57, 58 ' toughness test not required. MTR's a ttached. , 10,,11, 92, 94 Stainless steel containment sump j
' () _ ,,
lines. Fracture toughness test not required. 12, 13, 14, 19, 20, 24 Carbon steel penetration sleeves and 25, 26, 27, 29, 30, 31, nozzles (pipe caps) with wall thick- , 33, 43, 47, 48, 49, 50, nesses of 1" or less. Fracture
. 54, 55, 59, 61, 62, 63, toughness tests not required by 64, 66,.67, 68, 70, 73 Paragraph NE2300 of the Code thru 82, 85, 88 21, 22, 32, 34 thru 42, Carbon steel penetrations with at 44, 45, 46, 60, 65, 69, least some material greater than }"
71._72, 83, 84, 86, 87, thick: Sleeves, nozzles, (pipe caps), 89 thru 92, 95 thru 104 equipment hatch, personnel access lock and auxiliary access lock. Material test reports showing accept-able fracture toughness tests are included. l^ . . h u- _ Lj
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- GENERAL REQUIREMENTS FOR CONTAINMENT PENETRATIONS FRACTURE *
. FABRICATION TOUGHNESS TEST ACCEPTANCE '
PENETRATION CATEGORIES NATERIAL~ SPECIFICATION CODES REQUIREMENTS TEMPERATURE CRIIERIA COMENTS Only' carbon steel
~
Flued Head SA105 (as modified by ASME BPVC ASME BPVC 30 F. AFa5 BPVC . Section III Section III- Section III flued heads are
!N!!_M. . _
codeCase1519}$$$$~. SA182 F304 1971 Edition Susser 1972 Para. NC2300 Appendix I-Table I-7.1 considered since fracture toughness Addenda tests are not Subsection NC required for stain-less steel. ASME BPVC
- Elsctrical. G .E . Section III ASME BPVC 0F ASME.BPVC G.E. penetrations did PInetrctions SA182 - F304 1971 Editiou Section III Section III not exceed %" thick-SA240 - 304 Summer 1972 Para. NE2300 Appendix I ness for carbon SA105 - GR11 Addenda and Table I-7.1 steel.
SA312 - 304 1977 Edition Subsection NE
- 4 - Panatration Sleeses, Seamless Pipe ASME BPVC ASME BPVC -30 F for ASME BPVC N:nzles (Capa), !M33 a_ Grade,6,, Section III Section III Equipment Section III Equipment Hatch, Fittings Subsection NE Para. NE2300 Hatch. Appendix I - Parconnel Lock and . gg34 3, Grade,g B 1971 Edition O'F for Table I-7.1 . Auxilicry Access Lock Forgings Summer 1971 other items E#q}0,,(,gade,g Addenda Steel Plate SA516, Grade 70 ,
e 4 A
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T ' HECHANICAL PENETRATIONS MILL HEAT NUMBERS NETRATION SLEEVE CAP FLUEC HEAD 1 80lJ25770 (A) 4-2676 2 80lJ25770 (A) 4-2684 3 801J25770 (A) 4-2708 4 802J13199 (A 1-3440 5 802J13199 (A 1-3486 6 802J13199 1-3504 7 113379 4-2532 8 113379 (A 4-2586 9 313379 4-2586 10 .itainless Steel - NA 11 Stainless Steel . (A) NA 12 80lJ25820(D) A2225 NA 13 80lJ25820 A2225 NA 14 80lJ25320 (B) NA 15 802J15000 (J10713-2) A) 1-3632(D 16 802J15000 (J10713-1) A) 1-3591 (D 17 802J13460 (A) 1-3668 0 18 80lJ28569 (A) 1-4674 D) 19 113379 645J483 iM 20 113379 645J483 NA 21 62320 FT4HH NA 22 62320 IT4HH NA ('_') 23 113379 (C) 1-3629 (D) 24 113379 645J483 NA 25 224337 94624-26 NA 26 224337 94624-26 tM 2/ 224337 94624-26 NA 28 113379 (C) 1-3629 (D) 29 224337 C-E(D) fM 30 224337 94624-26 NA 31 224337 94624-26 NA 121035 IT4HJ1 NA 32 223610 GA4BH (D) NA 33 42794 IT4E NA 34 60217 IT4m IM 35 FT4E NA 36 42794 FT4m IM 37 42794 NA 38 62320 IT4HH1 62320 ET4HH1 E 39 NA 40 62320 ET4HH1 NA 41 62320 FT4HH1 00 42 A45256 FT4HJ1 NA 43 224337 94624-26 44 A45256 FT4HJ1 45 A45256 FT4HJ1 g 46 A45256 FT4HJ1 N4 47 223610 GA4BH (D) g ('# 48 223610 CA4BH g4 49 213748 CA4BH gg 50 213748 GA4BH(D) pg 51 224337 4-2532 52 2243:7 2L-2574 t .
e PENETRATION SLEEVE , CAP FLUED HEAD 53 224337 (A) 4-2532 54' 213748 GA4BH (D) ~ NA 55 213748 GA4BH (D) NA 56 H3379 (A) 1-3591 (D) 57 H3379 (A) 1-3090 (D) 58 113379 (A) 1-3632 (D) 224337- 94624 -26 NA 59 ' M4HH1 NA 60 62320 645J483 NA 61 H3379 - NA . 62 213748 GA4BH(D) CA4BH (D) NA 63 213748 NA-64 224337 FN4WH(D) NA 65 802J13460 FT4JHL NA 66 '213748 GA4BH(D) NA 67 213748 GA4BH (D) NA 68 64P148 GA4Bd (D) , NA 69 60277 FI4KH CA4BH (D)
*E 70 223610 M 71 121035 FT4HJ1 NA 72 12'1035 FT4HJ1 M
.73 213748 GA4BH (D) 74 213748 CA4BH (D 75 213748 GA4BH (D)) gp
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76 224337 94624 -26 f 77 224337 94620-26 g 78 224337 94624 -26 g O- 79 224337 94620-26 645J483 NA 80 . 113379 g 81 H3379 645J483 g 82 113379 645J483 g 83 , 121035 FT4HJ1 g 84 Equipment Hatch (See Attached) g 85 :Elae"4 e =1 Penetrations (See Attached) g 86 802K78860 80lK08329 (D) Personnel Lock gg 87 . 80lK08329 802K78860lD') Auxiliary Access Lock NA 88 Electrical Ground (B) NA 89 A45256 FT4HJ1 ' NA 90 A45256 FT4HJ1 N4 91 A45256 FI4HJ1 NA 92 A45256 FI4HJ1 NA ' 93 Stainless Steel (C) - NA 94 Stainless Steel (C) NA 95 60277 FI4KH NA 96 42794 FI4KH NA 97 802J13460 FI4JH1 NA 98 802J13460 FI4JH1 NA A45256 FT4HJ1 NA 99 100 A45256 FI4HJ1 NA ET4JH1 NA 101 802J13460 802J13460 FI4JH1 NA 145256 rr4ua1 "^ O 102 103 104 A45256 FT4HJ1 NA w_
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. NOTES ~ (A) Cap not required'with flued head.
- (B) Carbon steel material less than 1/2" thick.
t (C) Stainless steel material. i (D) Charpy impact test not noted and not required because of material thickness or because material is stainless i -- steel . i 4 e i i O
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p SUDSCRITED h.:D SWO3M TO ;EFORE ME 20!TR5770 . N nn3 h DAY CF, . . - 1973
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. . . MY COMpg1SSION EXPilt!;iSg MAY 10, 1975 Id W :r . c.rm .,
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INPACT PROPERTIES CUSTOMER: Chicago Bridge and Iron Company PAGE 3 ATTACHMENT hilIPl!ENT NO. 803-21023 12/24/72 D...ATE SH.I.P. PED F LONGITUDINAL CHARPY V-NOTCH. TESTED
... .. @ C-CHARPY SIZE FT. LBS . ,- % DUCTILE FRACTURE AREA LATERAL EXPANSION (TN)
SERIAL NUMBER HEAT NUMBER
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DATE SHIPPED 12/24/72 '.4
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hANI &*irMENT MO. 803-02314 1/05/73 PC LOUISVILLE LN PRR 475580 PAGEk
" URNS HARBOR CHICAGO BRIDGE AND IRON CO. CHICAGO BRIDGE AND IRON CO.- , .c. .n~ 2 BOILES, AL.
BOX 277 E .- BIDIINGAM, AL 35202' -- . .
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SUBSCRT ED AND_QWOD 1..:TO EETORE ME l20 1.1[ .0d ' ' nns/,fony;6f.~ - 801J28569. .
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RECORD OF HEAT TREATMENT h . CUSTOMER: Chicago Bridge and Iron Company $i *:r: PAGE . 3 ATTACIDfENT
'l 'I SHIPMENT NO. 8031023 4 DATE SHIPPED 1/05'/.7)
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. PLATE NORMALIZING CYCLE q i FURNACE T HIE ' g' -
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~ __. A-IMPACT PROPERTIES Si CUSTGMR: Chicago Bridge and Iron Company V PAGE 3 ATTACIDENT ,
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. SHIP)ENT No. 803-02314;;-
DATE SHIPPED 1/05/73%.(h
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LONGITUDINAL CHARPY V-NOTCH TESTED @ e' f fj (inh
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- SHIP 1ENT NO.
DATE SHIPPED 12/24/72 LONGITUDINAL CHARPY V-NOTCH TESTED G' - 4' :D FT. LBS. % DUCTILE FRACTURE AREA LATERAL EXPANSION (IN) (Q SERIAL NUMBER HEAT NUMBER CHARPY SIZE J33218 (2-7) dO2J1356D yu11 2 52 .[ 037);.F /
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# g. We hecoby c ortify the t the mater $ al herewith conforma 3553 ASME 3A-516 CBI Spec. MS-920 Rev. 0-4 S-31d Rev. O.
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{0 6-SUE 5CRIDED AND sworn TO BEFORE ME THIS . . O
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THAT TO THE DEST OF MY KNOWLEDG _ y _7 y , AND DELIE THE ADOVE R - RT 15 TRUE AND CORREC1
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