ML19263C350
| ML19263C350 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/14/1979 |
| From: | Groce R YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-12, TASK-3-12, TASK-RR WYR-79-15, NUDOCS 7902220022 | |
| Download: ML19263C350 (7) | |
Text
4 Telephene 6'7 366-0011 TW1 710-390-0733 YAll!WE ATOMIC ELECTRIC COMPANY s.3.2.1 2,,
s'i 20 Tudipt$o Road Westborough, Massachusetts 01581 Ej f 4
,Y/csixes WYR 79-15 February 14, 1979 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation Referenec:
(a) License No. DPR-3 (Docket No. 50-29)
(b) YAEC letter to USNRC, dated November 27, 1978
Dear Sir:
Subj ec t:
Systematic Evaluation Progran (SEP)
In our letter, reference (b), we submitted a complete tabulation of the Yankee Rowe environtental qualification of safety-related electrical equipment (SEP Topic 111-12). During our recent refueling shutdown, a design change was implemented whereby the level instrumentation on the diesel fuel day tanks was replaced, resulting in the change of two items in the tabulation.
We have enclosed revised tabulation sheets which include the qualifica-tion data for the newly installed equipment (Items 27 and 47), a revision to the documentation ref crences (Items d and 17), a revision to the original equipment list (Page 8), and a revision to Section E.28 of the original equipment qualification description (Pages 18 and 19). These revised pages replace and update the corresponding pages of our previous submittal, reference (b).
We trust this information is acceptable to you; however, should you have any questions, please contact Mr< David A. Hansen of this of fice.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY W
Robert H. Groce Licensing Engineer RHG/cm Enclosures 7 90 222 0 dBX r
<s 4
Reactor: Yankee Rowe Systematic Evaluation Program SEP Environment Submittal The Qual.
Equipment Type Reference Loc.
Uceded Parameter Spec.
Qual.
Method Reference Remarks 26 Switch 1-3/11 I
< 0.2 Temp.
244 F 280 F Test 66,67 Static-0-Ring /
F r. (Psia) 47 51 Test 66,67 7821-100 RII 100%
1007.
Test 66,67 Chem.
No
- 2 Rad.
2x10' 4x10 Test 66,67 Sub.
No 27 Transmitter, Level 1-8/2 0
Long Temp.
100 F 250 F V. Data 16 GEMS /
Pr.(Psia)
Anb 165 V. Data 16 XM800 Ell Amb 100%
Eval 16 Chem.
No
- 4 4
Rad.
10
> 10 Eval 45 Sub.
No 28 Switch 1-3/6 0
< 0.1 Temp.
90 F 100 F V. Data 21 Magnetrol/
Pr. (Psic)
Amb 515 V. Data 21 0-751-X1-SP-SIM3 Ril Amb Amb Exper Chem.
No
- 4
~
4 Rad.
10
> 10 Eval 45 Sub.
No 29 Switch 1-3/9 0
( 0.1 Temp.
90 F 180 F V. Data 3
Static-0-Ring 1-5/1 Pr.(Psia)
Amb Amb Exper
[
12N-S4-04-X2 Ril Amb Amb Exper 12NNL4-C Chem.
No
- 4 Rnd.
10
> 10 Eval 45 Sub.
No 30A Battery
'l-8/l 0
Long Temp.
90 F 110 F V. Data 53 C&D Battery /
Pr. (Psia)
Amb Amb Exper KU-15 RH Amb Amb Exper Chen.
No 4
Rad.
10
) 10 Eval 45 Sub.
No J
<r Systematic Evaluation Program Reactor: Yankee Rowe SEP "I# **"
Submittal Time Qual.
Equipment Type Reference Loc.
Nceded Parameter Spec.
Qual.
Method Reference Rccarks 47 Receiver, Level 1-8/4 0
Long Temp.
100 F 149 F Test 17 GEMS /
Pr. (Psia)
Amb Amb Test 17 RE-36520 RH Amb 1007.
Test 17 Chem.
No
- 4 4
Rad.
10
> 10 Eval 45 Sub.
No 48 Bistable 1-1/14 0
(0.1 Teep.
110 F 150 F V. Data 22,23 Rochester /
Pr. (Psia)
Amb Amb Exper ET-215R Ril Amb Amb Exper Chem.
No
- 4 Rad.
0.1
> 10 Eval Sub.
No 49
^
Alarm 1-1/16 0
< 0.1 Temp.
110 F 130 F V. Data 2C Sigma /
Pr. (Psia)
Amb Amb Exper 9222-20ED-2-VB11M RH Amb Amb Exper Chem.
No Rad.
0.1
> 10 Eval Sub.
No 50 Alarm 1-2/10 0
( 0.1 Temp.
110 F 122 F V. Data 59 Acromag/
Pr. (Psia)
Amb Amb Exper 871-S-8 Ril Amb Amb Exper Chem.
No Rad.
0.1
> 10 Exper Sub.
No 51 Ion Chamber 1-2/1,2 I
( 0.1 Temp.
110 F 176 F V. Data 27 Westinghouse /
Pr. (Poia)
< 26'
> 20 Test 65 WL6377 RH (100%
1.00%
V. Data 27 WL6937A Chem.
No
- 11 Rad.
4x107 2x10 Spec 50,68 Sub.
No J
YANKEE R0WE Documentation
References:
1.
March 9, 1972 Letter, Westinghouse to YAEC 2.
March 27, 1973 Letter, Westinghouse to YAEC 3.
January 16, 1974 Letter, YAEC to USAEC 4.
Deleted 5.
Novenber 30, 1977 Letter, YAEC to USNRC 6.
Deccaber 1, 1977 Letter, YAEC to USNRC 7.
January 20, 1978 Letter, YAEC to US"RC 8.
February 14, 1978 Letter, YAEC to USNRC 9.
Analogic Bul. 16-100056, Revision 2 10.
ASCO Bul. 8211 s
11.
ASCO Bul. 8302 12.
Bailey Drawing H6610183, Revision A 13.
Bailey Drawing H6610184, Revision A 14.
Bailey Spec. E21-7 15.
GE Measurement & Control Handbook 16.
GEMS Drawing No. XM-S00, Revision D
- 17. Test Report No. 2917-3S41, Lockheed Electronics Co.
18.
ITT Barton Bul. 199-2-1 19.
Lambda Spec. Sheets for LC & IM Series Power Supplies 20.
Leeds & Northrup Manual 177823 21.
Magnetrol Product Data, Model 751 22.
Rochester Bul. 214 23.
Rochester Bul. 401 24.
Rosemount Data Sheet 2235 25.
Rosemount Data Sheet 2260 26.
Sigma Spec Sheet, Series 9220 27.
Westinghouse Bul.57-451 28.
Westinghouse Bul.57-542 29.
Deleted 30.
Spec YA-719-Y 31.
Spec. YS-621 32.
WCAP 7410-L, Vol. I 33.
Assoc. Nucleonics Report AN-115, May 15, 1959 34.
Combustion Eng. Test Procedure ICE-TP-1 35.
Fischer & Porter Engineering Report " Nuclear Radiation Investigation" September 14, 1970 36.
Deleted 37.
FIRL F-C3441 38.
Deleted
- 39. FIRL F-C 3798 40.
FIRL F-C4124 41.
Collyer Technical Report #67-2 42.
USDC Report # APEX-261 43.
" Report on Effects of a Piping Break Outside Containment at Yankee Nuclear Power Station, Rowe, FL\\", July,1973
ID #
EQUIPMENT (DESC.-FUNC.)
MFR MODEL, TYPE OR CAT #
CLASS LO.;
ENV REQT ENV QUA Elect rical Equinnent DG-Generator Energency Diesel Gen DELCO E-4859VB IE PAB AS B27 DC-LT-Level Transa Level Cntrl Day Tnk GEMS XM 800 IE PAB AS B28 DC-SLCV-4 SOV Diesel Gen Day Tnk Fill Valve ASCO 8211B56 IE PAB A5 E20 DG-LR-Level Reevr Level Cntrl Day Tnk CEMS RE-36520 IE PAB A5 B28 No 1 Battery EXIDE FOP-13 IE SWGR A3 B3 No 2 Battery EXIDE FOP-19 IE SWGR A3 B3 No 3 Battery CSD KU-15 IE PAB A5 B3 No 1 Battery Charger - MG Set EPCO 70-D IE SWGR A3 B3 No 2 BatP rv Charner - MG Set EPCO 70-D IE SWGR A3 B3 No 3 Battery Charger - Static Co;' ARR130H IE PAB A5 B3 No 1 Battery Switchboard WES7 IE SWGR A3 B3 No 7 Battery Switchboard WETr IE SWGR A3 B3 No 3 Battery Switcanoard ILST CDP IE PAB A5 B3 No 3A Battery Switchboard UEST G-10F IE PAB A5 B3 No 3B Battery Switchboard WEST WFB-2W IE PAB A5 B3 480 Volt Energency Bus 1 GE ARD-5 IE PAB AS B3 480 Volt Energency Bus 2 GE ARD-5 IE PAB A5 B3 Connector Coaxial Type UN IE VC*
A2 B12 Page 8 J
monthly to assure proper operation. The only change in environment during the DBE is at the detector and the coaxial cable in the turbine building. The 120-day integrated dose is less than 1R which will have no adverse effect.
B.25 These transmitters ar ;w'.rilar in style to the pressuri:cr level transmitters discussed in Section B.6, except that they are rated for 1500 psia, rather than 3000 psia, and are of weatherproof con-struction, rather than explosion proof. The Buna-N 0-rings which provide the housing seals are rated for operation up to 212 F; however, these seals are not exposed to the external environment.
A scoping evaluation indicates that for the time the transmitter has to operate the temperature of the housing will not cause the 0-ring to fail. Since there is no radiation dose increase associated with the steam line break and continued operation is required for only a few minutes, there is reasonable assurance that the transmitters will provide a signal adequate to allow the operators to obtain a comparison of steam generator levels.
Reference:
B.25.1 Bailey Product Specification E21-7.
B.26 The recirculation fan motors have been designed to operate in an atmosphere of steam and dissolved boric acid at a temperatuge of 275 F and a pressure of 50 psig to an integrated dose of 10 R.
A prototype motor has been qualification tested at the Franklin Institute Research Laboratory and documentation is on file at YAFC.
Reference:
B.26.1 Specification YA-719-Y (rev. 4), Specification for Fan Motors for Ilydrogen Control System B.26.2 Letter, Westinghouse to YAEC, dated 3/9/72 B.26.3 Letter, Westinghouse to YAEC, dated 3/27/73 B.27 The referenced letter contains a complete description of the standby diesel generators as well as information regarding their satisfactory performance to date in their periodic testing and maintenance programs.
If loss of a-c occurs in coincidence with the LOCA DBE, the 30-day integrated dose of less than 10"R will have no effect on the diesel-generator.
(Reference B.1.6)
Re ference:
B.27.1 Letter, NYR 78-5, YAEC to USNRC, dated January 20, 1978,
Subject:
Standby Diesel Generator Questionnaire B.28 The Gems Icyc1 indicating system is designed for fuel oil day tank appli-cations.
In the fuel oil environment, the transmitter is designed to operate up to 250 F and up to a pressure of 055 psia. The receiver unit is designed for military applications and a similar unit has been tested to Mil-Spec environmental requirements for shock, vibration, temperature-hamidity, water spray, and electrical transients. The tests verify satisfactory operation at 149 F and with a water spray on the enclosure.
If loss of a-c occurs in coincidence with the LOCA DBE, the 30-day 4
integrated dose of less than 10 R will have no effect on the level indi-cating system.
Reference:
B.28.1 Gems Drawing No. XM-800, Revision D 18
B.28.2 Test Report No. 2917-3841, Lockheed Electronics Co.
B.29 Terminal blocks used inside containment are enclosed in protective boxes and their environmental qualification has been discussed with NRC and addressed in the referenced letters.
Terminal blocks which are used throughout the plant outside containnent and are exposed to nuch less severe environmental conditions.
Reference:
B.29.1 Letter, YAEC to USNRC,
Subject:
IE Bulletin
- 78-02, Terminal Block Oualification, dated Feb rua ry 14, 1978.
B.29.2 Letter, USNBC to YAEC,
Subject:
Sunmary of Meeting 2/1/78 concerning Yankee Rowe, dated February 3,1978 B.29.3 Letter, Westinghouse to YAEC, January 31, 1978 B.30 The references contain qualification inforcation for the penetration assemblies at Yankee Rowe.
Reference:
B.30.1 YAEC letter to USNRC dated November 30, 1977, WYR 77-116 B.30.2 YAEC letter to USNRC dated December 1, 1977, WYR 77-118 B.30.3 Test Report:
Associated Nucleonics, Inc., AN-115, dated lby 15, 1959 B.30.4 Letter, YAEC to USNRC, dated 12/12/77 B.31 The equipment within the containment to which cables are connected consists of a valve notor, recirculation fan totors, and instrutents.
Equiprent which was originally installed in the plant was wired in a consistent canner. Instrumentation wiring within the loop conpartnents and the pressurizer comparttent consists of mineral insulated cable to a junction box outside the biological shield wall; and fron there, polyethylene insulated cabic with a PVC jacket in conduit to the penetration.
Siniiarly, the power and control wiring for valve notors consists of nineral insulated cable within the biological shield wall; and from there, either polyethylene or butyl rubber insulated cable with a PVC jacket in conduit to the penetration.
Instrumentation and rotors which were installed later in plant life were connected by cables in conduit from the equipment via enclosed junction boxes to the penetrations. This equiprent.is specifically the recirculation fan motors, the LTOP transmitter, the stean generator narrow range level traasnitters for reactor protection,
~
the main coolant pressure switch for safety injection initiation, and the solenoid valves for hvdrogen sanpling. PVC shielded cables were specified for these installations, unless otherwise noted in 19 r
.