ML19273B914
| ML19273B914 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/12/1979 |
| From: | Counsil W NORTHEAST UTILITIES |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| TAC-42493, NUDOCS 7906180496 | |
| Download: ML19273B914 (17) | |
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IW)ll'i1IIIA!;T tlTil.ITII!!i P o BOX 270
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HARTFORD CONNECTICUT 06101
(
(203) 606 6911 g
g m
June 12, 1979 Docket No. 50-336 Director, Division of Reactor Operations Inspection Attn:
Mr. Norman C. Moseley Of fice of Inspection and Enforcerant U. S. Nuclear Regulatory Commission Washington, D. C.
20555
References:
(1)
B. H. Grier letter to W. G. Counsil dated February 8,1979, forwarding I&E Bulletin 79-01.
(2)
W. G. Counsil letter to B. Reid dated March 23, 1979.
(3)
W. G. Counsil letter to R. Reid dated April 6, 2 >79.
(4)
W. G. Counsil letter to R. Reid dated April 18, 1979.
(5)
W. G. Counsil letter to R. Reid dated May 8,1979.
(6)
R. Reid letter to W. G. Counsil dated May 12, 1979.
(7)
B. H. Grier letter to W. G. Counsil dated June 6,1979.
Gentlemen:
Millstone Nuclear Power Station, Unit No. 2 Environmental Qualification of Class lE Equipment In Reference (1), Northeast Nuclear Energy Company (NNECO) was requested to respond to four NRC Staf f concerns regarding the environmental qualification of Class lE equipment.
'.n response to Item (4) of Reference (1), NNECO sub-mitted References (2) through (5), for those instances when the appropriate environmental qualification documentation could not be produced.
NRC Staff review and acceptance of NNECO's actions with respect to these components was documented in Reference (6).
In direct response to Item (2) of Reference (1), please be advised that, excluding the stem-mounted limit switches (SMLS) identified in References (2), (3), and (5), NNECO has not identified any SMLS's in the containment which are not suitable for service in the LOCA environment, in that their associated valves will perform their design functions.
In response to Item (3) of Reference (1), Attachment 1 is provided.
Included in the Attachment in the form of equipment lists are:
(a) Component description; (b) Description of the accident environment; (c) The environment to which the equipment is qualified ;
(d) The manner of qualification; and Identification of the specific supporting qualification documentation.
(e)
Ef forts to date have focused on Class lE equipment located within the contain-ment building. Areas of omission are the result of qualification information 2354 022 7906180 $/ff.
. which is being obtained from the equipment manufacturer or areas where addi-tional investigation is required.
It is currently anticipated that this portion of the effort will be completed and a supplement to this submittal docketed on or about August 31, 1979.
A similar program for Class lE equipment located outside containment is also in progress at this time, at a lower priority than equipment within containment.
A second supplement to this submittal on this segment of the program is scheduled to be docketed on or about October 31, 1979. The basis for continued operation at Millstone Unit No. 2 is the adequacy of the equipment qualification compiled to date, and the short interval of time anticipated to resolve the remaining NRC Staff concerns.
Reference (7) was received only two days ago and is currently being evaluated.
The subject ASCo valves will be the topic of future correspondence.
We trust you find the attached information responsive to your concerns.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY 1
/
TIM 104 W. G. Counsil Vice President Attachment cc:
Mr. B. H. Grier Director, Region 1 Of fice of Inspection and Enforcement 023 U. S. Nuclear Regulatory Commission King o f Prussia, PA 19406
DOCKET No. 50-336 ATTACilMENT 1 MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 ENVIRONMENTAL QUALIFICATION OF CLASS lE EQUIPMENT 2354 024 JUNE, 1979
NOTE 1 The specified post incident conditions include a pressure of 54 psig, however, tha peak test pressure achieved uas 5 2 poig.
This discrepancy is considered insignificant since the merimum calculated containment pressure (51.2 poig per FSAR Amendment 39, Paragraph 14.10.1) is within this limit.
It is also noted that the cabic manufacturar certifice that he has revicued the specified requirements and considers the Franklin Institute Report to be at least comparable in severity to these requirements.
NOTE 2 The environmental qualification of valves CH-518, CH-519, EB-91, EB-100 uas addressed in the W.
G.
cJansil letter to R.
Reid, dated Apell 18, 1979.
The ASCO letter to Hortheas t Utilitics dated June 1,
1979 defined a u ' voltage condition as 90 to 109 VDC uhich is more restrictive than the 90 to 100 VDC discussed in the above April 18, 1979 letter.
Also, the ASCO letter states that additional information could be required to qualify the operation of these valves after tueluc (12) hours into an accident.
The effcets on qua lifica tion of the latest ASCO letter is being cualuated.
NOTE 3 The SMLS on these valves acre not replaced prior to the Cycle 3 operation.
Investigation of those valves has shoun that SMLS failure uill not prevent the valves from attaining their accident position.
In addition, regarding EB-38 and EB-89, there is an alterna te means of obtaining the desired sampic.
(Sec FSAR Ques tions and. nsucre G.23.)
requirements for sampling Regarding LRR-61-1, there are no the primary drain tank in a post-LOCA condition.
2354 075
. NOTE 4 UOTE #4 DELETED.
NOTE 5 Environmental qualification data for the containment temperature monitoring RTD assemblies is not presently avail-able.
Rosemount Engineering is presently researching this subject.
Submittal of this information vill follou our cualuation of this data when received.
NOTE C Environmental qualification data for these components uas obtained from the equipment specification, and confirmed by a Certificate of Compliance to the specification require-monts.
The specif *ed environmental parame ters for these components are defined by the respective equipment specifica-tion.
2354 026 RJD:cau G/08/."9
4 DOCUMENT REFERENCE LIST 1.
Combustion Engineering Specification 18767-ICE-903, Rev. 3 Spec Sheet 1 2.
F.I.R.L. Report F-C3635, " Maximum Credible Accident Environment Test of Four Transmi tters".
3 The Foxboro Company Test Report No. T3-1097, " Radiation Test of E-10 Series Amplifiers Standard and Radiation Resistant Types".
4.
Combustion Engineering Specification 18767-lCE-903, Rev. 3, Spec Sheet 216.
5 Northeast Utilities File Letters, HP2-CE-2862, 8-MP2-2711, B-MP2-2706, MB-4554.
6.
Combustion Engineerina Specification 18767-lCE-903, Rev. 3, Spec Sheets 212 and 230.
7 The Foxboro Company Test Report No. T3-1068, " Radiation Test of E-10 Series Oif ferential Pressure Transmitters of the MCA/RRW Type" 8.
Combus tion Engineering Speci fication 18767-lCE-903, Rev. 3, Spec Sheet 25 9
The Foxboro Company, Test Report No. T4-6040.
10.
Combus tion Engineering Speci fication 18767-ICE-903, Rev. 3, Spec Sheet 28.
11.
Bechtel Speci fication M-470A.
12.
Combus tion Engineering Speci fication 18767-ICE-903, Rev. 3, Spec Sheet 56.
13 Combustion Engineering Specification 18767-ICE-903, Rev. 3, Spec Sheet 195 2354 027
DOCUMENT REFERENCE LiS (page 2) 14.
General Electric Product Description / Environmental Specifications.
15 Combustion Engineering Specification 18767-ICE-903, Rev. 3, Spec Sheet 194 16.
Combustion Engi neeri ng Speci fication 18} 67-lCE-488-105 2354 028
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A 2354 031
MILLSTONE NUCLEAR POWER STATION, UNIT NO, 2 PLANT NAME:
DOCKET NO. 50-336 A CCI:ENT ENVIFC% MENT (ICCA TION)
TIME QUAL.
D0C.
ITEM
_ EQUIPMENT DESCRIPTION REQ'D.
PARAMETER SPEC.
_ QUAL.
METHOD REF REMARKS 12 STE.'? MOUNTED LIMIT SWITCH POST LOCA CON TA INMEN T Prototvre Veno r Ce r t's These limit switches were NAMCO CONTROLS: TYPE Terp. ( F) 289 340 Test 4/27/79 instatted *av 1979 (Refyr EA-ISO Press. (pstg)
$1, 70 5/04/79 to w;;ounsil Letter to 100 Water Spray RReid; 4/06/79) huSCO P.O.
Rel. Hum.
B Radiation 8.2 x 106 2.04 x 10 R 607356 Chem.
1720 m Boron caustic Soray 13 STEM MOUNTED LIMIT SWITCH POST LOCA Prototype
'/endor Certs These limit switches were NAMCO Cont rols; Type T e@. ( F) 340 Test 4/27/79 installed May 1979 (Refer EA-740 Press. (psig) 63 5/04/79 to WSCounsil letter to Rel. Hum.
i Water Spray RReid; 4/06/79) NUSCO P.O.
3 Radiation 2.04 x 10 R 607356 Chem.
j Caustic Spray 14 ELECTRIC CONDUCTOR SEAL POST LOCA Analvtical CONAX These asse-blies installed ASSEMBLIES FOR S*1LS's IET
- I}
340
& 1 to 1 IPS 400 _
Mav 19 & lUSCO P.O.
CCNAx Part Nos. N-11001-32.
Press. (psig) 1 60 co narison c vendor 607386 Rel. Hum.
100 ith tested Certs N
y_;;gg;_33 6
units u
Radiation 1.5 x 10 W
~
Chem.
Coron & Naos 45 15 SET SCREW CONNEC(CRS IDEAL POST LOCA NJ5CO Memos Cont ai nment -LOC A E n vi ron -
C Tenp. (o )
289 Tests and CEE-79-271 ent-Coanecters are housed IND.
Cat. No.30-210 s F
N 30-211; used for splices Press. (psi g) 54 analvses GEE-79-214 in ventilated junction Cat. I De v i c e s to Cab e Ral. Ilum.
1001
- EE-78-355
-'-boxes; NUSCO P.O.
LTGn 7U ' T Urhoter2 6 o r2-bo ron 607737 P.adia tion and water Chem.
MILLSTLNE NUCLEAR POWER STATION, UNIT NO. 2 PLANT NNiE:
DOCKET NO, 50-336 3
ACCICENT ENVIPCNMENT (LO CA TICN)
TIME QUAL.
D0C.
ITEM EQUIPMENT _ DESCRIPTION req'D.
PARAMUER SPEC.
QUAL.
NETH00 REF
_ REPARKS 16 V ALVE S CH-518, CH-519; POST LOCA cc.;M 75'/FN T Vendor Certs Valves require p o operate Charn.Line Distr. Valves TeFU. ( F) 289 Fisher Letter following a LOCA. ASCO Press. (psig) 54 to Bechtal Cert of operation Letter PE!W-Ac t-F i s her Controls Rel. Hum.
100 1/02/76 6/01/79, Bechtel Spec 7604 Co. ASCO Sol. Valve Type Radiation 8.2 x 106 409A. E i.0; See Note 2 M
hat-8320A 90V Serial,
77965A 1720 ppm Baron S"LS Type EA-180 (item 12)
Chem.
17 VALVE CH-517 P05' '"
~
Testing of
-4,44 _ ' ;
LCC;
- /%
valve required to operate IeEP. ( F) 340 Valves of FO.607692; SPLS Type Aux. Spray PENU. Act. Fishr Press. (psig) 70 c.ener l y _.
_value installed t'ay.1979 -
Controls Co., ASCO Sol.
Rel. Hum.
IEEE 332 TAB 10 equal c sign.
( ref e r t o WGCouns i l letter Valve Tyre 205-381-6pF
~ ~~
0 Radiation 2x 10 Chem.
IEEE 382, TAS 16 Vendor Certs Valves fail closed 18 VALVES CH-515; CH-516 Aprox. 5 Sec.
Fisher Letter (acciJent position) ASCO Contm. Isolation Valves following a Tenp. ( F)
Pr'ess. (psig)
I to Bechtel:
Cert. of operation letter PENU.ACT. Fisher Controls LOCA Rel. Hum.
2/24/76 6fq1/70- Bechtel Specs Co.
ASCO Sol. Valve Tyr, HXT 8320A 90V, Serial #
Radiation 7604 F409A. E40; SMLS T3pe 6570B Chem EA-190 (iten 12)
Valves fail closed 19 VALVES EB88, EB39 Aorox. 5 Sec Terp. (UF)
(accident pcsition). A50C Conto. Rad. Mon. Iso. Val.
Followinq a
.N PENU.ACT. Fisher Controls LCCA Press. (psig)
Cert. of oceration letter Co., ASCO Sol. valve Type Rel. Ilum.
6/01/79; Cechtel Specs A
7[04"409A, E40; see Note 3 W
WPHT 8300661 RVU; Serial Radiation
.8d5 BOA Chem.
I
-__::=_-_m_==-----=_-.=__=_:-_
'A
'A
MILLSTT;E NUCLEAR POWER STATION, UNIT NO. 2 PWT WE.
DOCKET NO, 50 336 A CCI:ENT ENVIECNMENT (LOCA TION)
TIME QUAL.
00C.
ITEM
_ EQUIPMENT DESCRIPTION REQ'D.
PARAMETER SFEC.
QUAL.
METHOD REF REMARKi Administ atively closed 20 VALVES AC-5. AC-6 N/A cgy7A75ygg7 Con tainmen t c urae valves Tem. ( F) 289 (accider t position);E! ct.
penumatic actuators; Fisher Press. (psig) 54 Qua' Not required; Bechtel Csntrols Co; ASCO Sol. Val.
Rel. Hum.
100 Specs 7604 M229; E40; SMLS Type HTX 8316C45V Radiation 8.2 x 106 Type EA-180 (Item 12)
Ehem.
1720 rpm Boron 21 VALVES LRR 43.1, GR 11-1 Aprox. 5 Sec Vendor Cert.
Valves fall closed f II wing a Te w. ( F)
ASCO letter (a;cident position). ASCO CH-506. SSP 161; Contn.
Iso. Val. Pena.Act.
Mason - LOCA Press. (psig) to nasoneitar cert. of operation letter TN'"CPki Bhhb7)P gh) -
Rel. Hum.
1/23/73 6/01/79; Bechtr' specs 7604 I
72655A;96586A and 16005D Radiation M409S, E40; SMLS Type Chem.
{
EA-740 (ltem 13) 22 VALVES RC-001, 002, 003 Aprox. 5 Sec l
Vendor Cert.
Valves fail closed Te m. (*F)
I ASCO tetter (accident position), ASCO RC sa ple valves penu.act.
following a tiasoneilan; ASC'. Sol. Val.
LOCA Press. (psig)
_to %soneitan cert. of orcration letter 6/01/79; Bechtel Specs 7604 Type WPHT 8300861F; Serial Rel. Hum.
1/23/73
- 4098, E40; SMLS Tyce F72659A Radiation l
EA 740 (! tem 13)
Ehem.
N 23 VALVES EL-91. EB-100 POST LOCA Vendor cert.
Valves requi red to ope rate Hyd. purge iso, val. penu.
Tem. ( F)
Fisher letter following LOCA. ASCO Cert.
'J act. Fisher Controls Co.
Press. (psig) to Bechtel of operation letter 6/1/79 g
Rel. Hum.
11/9/73 Bechtet Specs 7604 M229, ASCO Sol. Valve Type HT.
E40; See Note 2 C
834445V Serial *198208 Radiation I
SMLS Type EA 740 (Item 13)
Chem.
4
MILLSTCNE N'JCLEAR POWER STATION, UNIT NO. 2 PLANT NAME:
DOCKET NO. 50-336 ACCIDENT ENVIRONMENT (LOCA TION)
TIME QUAL.
D0C.
ITEM EQUIPMENT DESCRIPTION REQ'D.
PARAMETER SPEC.
QUAL.
METHOD REF
_ REMARKS Valve is raintained closed 24 VALVE tRR-61-1 N/A ccyr,tygygNT Qacnch Tank cooler cont.
Terp. ( F) 299 (accident cositten) by ad-
.,inistrative centrols; iso valse penu.act. Mason-Press. (psig) 54 eechtel Specs 7604 M4033 eilan, t r;c., ASCO Sol.
Rel. Hum.
100 Valve Tvae NT 8320A26 Radiation 8.2 x 106 E40; See Note 3 Chem.
1720 rpm Boron 25 VALVES s1 614. 624. 634 N/A j
Seq. Tests Li-itoraae Valves aJninistratively 644; Safety injection tank Temp. ( F) 300 plus Vendor Project controlled cren (accident Press. (psig) 70 Cert. 5/25/79 Report position) Tech Spec iso. salves,. elan o ve Corp. MOV's linitor-op's Rel. Hum.
100 600456 3 5-1A; Bechtel Specs 7604 S/4 157040, 157041, 157042 Radi a tion 2.04 x 108 M223A. Ei.0. E 118 157043 Chem.
', *((r % 2 '
26 VALVES S1651. 51652 N/A hq. Tests Limito g e Valves in ter loc' ed to ore-
=
Terp. ( F) 300
- lus Vendor Project vent opening ducirq opera-Shutdown cooling iso. valv s
Velan Valve Corp. NOV's, Press. (psig) 70 Cert. 5/25/73 Report tion. Bechtel Soecs 7604 Rel. Hum.
100 600456 L imi to rq ue Oo's; S/N M_223A. E40 d 118 8
155532 155533 Radiation 2. 0 :. x 10 T
Chem.
itEf*ja}
y,,y,,
7,;, tim
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27 VALVES S1618. 623. 633,646 No Post Lor,
~ M M M T M Ae,aEIV ~
M Recu. ire ent T eitp. (o )
F r
c osc4 St Tank Test & Fill Valves ff Penu.Act. Fisher Controls Press. (psig) sechtel Snee., 7604 M781 A
Co., ASCO Sol. Valve Type Rel. Hum.
SMLS type EA-180 (See item HTX 8320C2 7R P.a di a tion, 12)
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MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 PLMT WE.
DOCKET NO. 50-336 ACCIDENT ENVIRONMENT (LOCA TION)
TIME QUAL.
00C.
ITEM
_ EQUIPMENT DESCRIPTION REQ'D.
PARAMETER SPEC.
QUAL.
METHOD REF REMARKi 36 Safety injection Tank N/A coNTAINyrNT Test See Note 6 Level Transmitter; GE No Post LOCA Terp. ( F) 289 135 13.14 GE/MAC Model 555 Req u i remen t Press. (psig) 54 At mspheric 13.14 Rel. Hum.
ion 100 13,14 Radiation 8.2 x 106 1R/HR 40 yrs 13.14 Chem.
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.j e e 'a c t e 6 Level Switch Moore Model No Post LOCA Temp. ( F) 130 15 215430 Requirernnt Press. (psig)
Atmospheric 15 Rel. Hum.
95 15 Radiation IR/HR 40 yrs 15 Chem.
15 38 Ju.'
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Out No Post LOCA~
IeW- ( f) 300 16 of Cort Neutron Detector Requirement Press. (psig) 65 16 Reuter Stokes Rel. Hum.
100 16 Radiation 3x 104 R/HR 16 Chem.
39 Connector for item 12 N/A f
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Type HM No Post LOCA Te m. ( F) l 30 16
_A Requirement Press. (psig) 65 16 J
Rel. Hum.
100 16 Radiation 5 R/HR 16 C
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