ML20138C008

Submits Addl Info Re Util 860225 Equipment Qualification Ltr for NRC Review,Per 860307 Discussions.All Electrical Equipment within Scope of 10CFR50.49 Environmentally Qualified.Supporting Documentation Encl

ML20138C008
Person / Time
Site:	Hope Creek
Issue date:	03/31/1986
From:	Corbin McNeil Public Service Enterprise Group
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8604020058
Download: ML20138C008 (30)

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Public Service Electric and Gas Company

'l Carbin A. McNeill, Jr.

Public Semce Electnc and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Vice Presicent-Nuclear March 31,1986 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission ~

7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:

Ms. Elinor Adensam, Director Project Directorate 3 Division of BWR Licensing

Dear Ms; Adensam:

COMPLETION OF ENVIRONMENTAL QUALIFICATION

. HOPE CREEK GENERATING STATION DOCKET NO. 50-354

. Pursuant to our discussions with H.

Garg and D.

Wagner on March 7, 1986, the following additional information, regarding Public Service Electric and Gas Company's equipment qualification letter dated February 25, 1986 (C.A. McNeill, PSE&G to E.

Adensam, NRC) is provided for NRC review.

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Limitorque Motor Valve Operator Wiring (I&E Information Notices 83-27 and 86-03)

Bechtel Specific Work Plan / Procedure SWP/P-E-18, " Termination i

Installation", references project-design documents; Electrical Cable Description (E-1000-0) and Wire and l

Cable Notes and Details (E-1408-0).

Appendix A of SWP/P-E-18 indicates the. criteria used by Bechtel for l

inspection of Limitorque operators.

The inspections performed by Bechtel included insuring compliance with applicable drawings and standards for the wiring used in the operators.

Therefore, a field check of all safety-related Limitorque operator wiring at Hope Creek confirms that the 5. iring is qualified.

Documentation regarding these inspections, as well as all EQ documentation, is available for audit.

I 8604020058 860331 Mk PDR ADOCK 05000354 l

l il

-A PDR'

3/31/86 Director of Nuclear 2

Reactor Regulation 2.

EQ-Summary Report, Rev. 4 - Equipment Evaluation Summary Sheets'(EESS)

The attached Addendum to the EQ Summary Report, Rev.

4, includes the following revised sheets, with any associated enclosures, as resolutions to EQB questions:

EESS

1. 030 EESS #124

1. 031

1. 132

1. 035

1. 134

1. 045

1. 165 These revised sheets should lua inserted in place of those submitted with the HCGS EQ Summary Report, Rev.

4, by letter dated February 25, 1986.

3.

Limitorque Valve Operator Motor Failure (I&E Information Notice 86-02)

As stated in the February 25, 1986 letter, alternate shutdown cooling is initiated-in accordance with-procedure OP-AB.ZZ-142Q or OP-EO.ZZ-205Q should the RHR shutdown cooling suction inboard containment' isolation valve (lBCHV-F009) fail prior to being properly aligned for long-term core and containment cooling.

The valve failure mode is fail-as-is.

As stated in the February 25 submittal, the power supply for the valve operator is protected with double breakers, with contactors open with the valve in the open or closed position.

The valve is not interlocked with any other components.

As indicated in EESS #132 (see attached

-Addendum), per GE Information Letter, SIL No. 425, dated July 17, 1985,-the valve operator is qualified to be operable for at least seven (7) days following a LOCA in the containment.

Valve position indication is based upon movement of the valve stem in conjunction with a limit' switch.

When the plant operator attempts to energize this valve from the Control Room, should the valve fail in the closed position, only the~ green indication lamp would' remain on.

If the valve fails while opening (i.e.

partially open valve), both the green and red indication lamps would remain on, and if the valve fails in the fully open position, only

'the red indication lamp would remain on.

Therefore, the plant operator is made aware of the valve's alignment for long-term cooling.

3/31/86 Director of Nuclear 3

Reactor Regulation A review of the alternate shutdown cooling procedures has been made to confirm that equipment used to establish long-term cooling are qualified within the scope of 10CFR50.49.

The review concludes that for each of the alternate shutdown cooling procedures, equipment used to establish long-term cooling is qualified.

In conclusion, the failure identified in I&E Information Notice 86-02 has been evaluated and found not to be a safety concern for the Hope Creek Generating Station.

4.

Drywell Atmosphere Post-Accident Radiation Monitor (DAPA) - General Atomics (GA) Ion-Chamber Detector (RD-23)(Ref. EESS #035)

Qualification of the DAPA Detector (RD-23) to the requirements of NUREG-0588, Category I, has been questioned considering the statement in GA's Qualification Report, E-254-960, that no thermal aging or radiation exposure testing was performed on the Reuter Stokes RS-C3-1006-201 Ion-Chamber Detector, RD-23 (S/N Y-501).

PSE&G requested GA to justify that thermal aging and radiation exposure testing of the RD-23 detector have been adequately addressed.

GA has furnished additional information which verifies the following:

a)

GA has conducted qualification tests on an RD-6 detector which contained a Reuter Stokes, Model RS-C4-1606-209, GAMMA Ion-Chamber.

This detector, which is similar to RD-23, was thermally aged for 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> at 225 C prior to seismic and LOCA/SLB environmant testing.

The detector completed all the qualification tests successfully and the results are documented in GA Report, E-255-1047.

b)

RD-23 detector, S/N Y-501, qualification tests, which were performed at Wyle Laboratories and were reported in GA Report, E-254-960, included exposure of the detector to three LOCA profiles.

One of these profiles included a test to 350 F @ 70 psig which can be considered.to represent the Hope Creek requirement of 340 F @ 62 psig.

The other two LOCA profiles which included tests to 400 F-175 F for about 1.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, 320 F for 1 hr, and 152 F for 4 days, can be considered as equivalent to thermal aging, having stressed the detector welds and seals beyond normal operation levels.

J 3/31/86 Director of Nuclear 4

Reactor Regulation c)

RD-23 detector, S/N Y-501, the specimen referred to in GA Qualification Report, E-254-960 which is listed in EESS #035', was recalibrated in November 1984 after being in storage for more than four years, and found to be within 15% of the original calibration made in March 1980.

The LOCA tests Therefore, in.the' report were performed in June 1980.

the detector remained fully functional and within calibration for more than four years after the qualification tests.

i d)

The life o'f an RD-23 detector is determined by the ability of the detector to maintain calibration.

Replacement is made when the detector sensitivity falls outside of its required range.

e)

RD-23 detector, S/N Y-8170, was subjected to tests which included irradiation exceeding a TID value of lx107 rads using a dose rate of 5x106 R/hr.

i This irradiation caused no change in the detector performance.

This is documented in GA Report, E-255-978.

In addition, Reuter Stokes, the manufacturer of the RD-23 detector, certified in their letter of February 27, 1981 1

(T.B. Fleming, RS, to D.

Peat, GA), that there are no materials contained in the detector which could cause it to be susceptible J

to significant degradation due to thermal and radiation aging.

t Based on the above considerations which give evidence of supporting test data, it is concluded that the RD-23 DAPA Ion-Chamber Detector for the Hope Creek Radiation Monitoring System is qualified to NUREG-0588, Category _I.

EESS #035 has been revised to include the two GA reports referred to in (a) and (e) above (see attached Addendum).

i-Also included in the attached Addendum are revisions to EESS #029 and #155A to reflect the replacement of Tobar L

transmitters with Rosemount transmitters as discussed in our letter dated March 26, 1986 (C.A. McNeill, PSE&G, to E. Adensam, NRC).

These revised sheets should be inserted in place of those submitted with the HCGS EQ Summary Report, Rev.

4.

4

3/31/86 Director of Nuclear 5

Reactor Regulation With this additional information, Public Service Electric and Gas Company confirms that all electrical equipment within the scope of 10CFR50.49 has been environmentally qualified.

Sincerely, fY N

x Attachment C

D.H. Wagner USNRC Licensing Project Manager R.W.

Borchardt USNRC Senior Resident Inspector H.

Garg USNRC EQ Branch 1

n-ENVIRONMENTAL QUALIFICATION

SUMMARY

. REPORT ADDENDUM NO. 1 TO REVISION 4 ITEM REASON 1.

EESS #29 Revision 5 Deleted seven (7) transmitters (replaced with Rosemount 1153's.per EESS

1. 155A) 2.

EESS #30 Revision 3 Add missing page and information under qualified temperature 3.

EESS #31 Revision 1 Added Note 5 4.

EESS #35 Revision 1 Clarified aging qualification method and revised documentation reference D 5.

EESS #45 Revision 3 Deleted aging qualified temperatures, replaced with Note 2 6.

EESS #124 Revision 5 Revised Note 3 7.

EESS #132 Revision 4 Added Note 5 8.

EESS #134 Revision 3 Revised Note 1 9.

EESS #155A Revision 3 Added seven (7) transmitters (deleted Tobar transmitters from EESS #29) 10.

EESS #165 Revision 3 Added Note 2 11.

3.11-5 Table Pages 10, Incorporated correct EESS 12, 54 No. 155A inplace of 29, to reflect changing of seven (7) 32 Series 2 Tobar Transmitters to Rosemount 1153 transmitters.

12, 3.11-5 Table Page 119 Added Note #6.

13.

EESS Index #29, 155A Revised number of components.

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HOPE CREEK GENERATING STATION EESS INDEX Page 2 NO. OF REF.

EESS NO.

COMP-NO.

DESCRIPTION ONENTS STATUS 16 F37917-TFB-001 Buchannan Terminal and Fuse Block G(17) Complete 17 RESERVED k

18 RESERVED 19 F43620-HVT-001 RayChem High Voltage Terminal Kit G(1) Complete 20 F47888-MCON-001 RayChem N-MCK Motor Connection Kit G(1) Complete 21 F48479-SEAL-001 RayChem Cable End Sealing Kit G(2) Complete 22 F48561-TINS-001 Raychem Thermofit Insulation G(1) Complete 23 F48561-SPL-002 RayChem WCSF-N Splice G(1) Complete 24 F51216-SEAL-001 Conax Electrical Conductor Seal Assembly G(1) Complete 4

25 J201-HS-001 Micro Switch Selector Switch 14 Complete 26 J201-AMP-002 AMP Wire Lug G

Complete 27 J201-TFB-003 Buchannan Terminal and Fuse Block G(4)

Complete 28 J301-T-001 Tobar Instrument Transmitter (32 Series #1) 18 Complete 29 J301-T-002 Tobar Instrument Transmitter (32 Series #2) 46 Complete 30 J359-VAR-001 Comsip Hydrogen & Oxygen Analyzer 50 Complete 31 J359-VAR-002 H /02 Heat Tracing Panel 12 Complete 2

32 RESERVED 33 F61553-PG-001 Modified Conax PG Gland Assembly G

Complete 34 F681'59-TE-001 Weed Temperature Element 2

Complete 35 J373-RE-001 DAPA-GA Ion Chamber Detector (RD-23) 2 Complete 36 J373-RE-002 RBE/RFE Inline Beta Detector - RD25A 6

Complete

HOPE CREEK GENERATING STATION EESS INDEX Page 8 NO. OF REF.

'EESS NO.

COMP-NO.

DESCRIPTION ONENTS STATUS 144 P305-HV-002(+ZS)

Limitorque A.C. Motor Operator 74 Complete 145 P305-SV-003 ASCO Solenoid Valves 13 Complete 146 P305-ZS-005 NAMCO Limit Switch 17 Complete 147 P305-HV-004(+ZS) BIF/ Paul Monroe Hydraulic Actuator Assembly 8

Complete 148 RESERVED 149 M001-LT-036 Gould Level Transmitter 1

Complete 150 M001-LS-023 Magnetrol Level Switches - Cll 2

Complete 151 M001-LS-024 Magnetrol Level Switches - Cll 4

Complete 152 M001-SW-025 G.E. Selo-: tor Switch, CR2940 - C12 2

Complete 153 M001-CONN-026 PRM Connectors - C23A/24A 1

Complete 153A M001-CONN-026 IRM Connectors - C23A/24A 1

Complete 154 M001-EAM-027 G.E. Voltage Pre-amplifier - C25 8

Complete 155 M001-XMIT-028 Rosemount Pressure Transmitter ll53B-C59 131 Complete ISSA 119812-XMIT-001 Rosemount 1153B Transmitters Utilizing 44 Complete Output Code "R" Electronic Circuit Board 156 P1-113281/945872 Rosemount 1153B Transmitters 2

Complete

-XMIT-001 157 M001-ST-030 Terry RCIC Steam Turbine Assembly-S08/SO9 9

Complete 158 M001-LS-031 NAMCO MSIV Limit Switch - S05B 8

Complete 159 M001-SRV-032 Safety Relief Valve - S20 19 Complete 160 M001-HV-033 MSIV Actuator - S21 24 Complete 161 M001-PS-034 Barksdale Pressure Switch - C09 4

Complete 162 RESERVED 163 M786-FUSE-003 Bussman Fuse G

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asidfee<5res-=<AP..>and non-permanent lubricatten shall have a stalmue

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2. New 0-Ring is to be used when cover is repined af ter calibra-Lien Ref. Pg.5 C. Vender Report No. J301(Q)-66(2)-I IIII 88"E3M "U'8-

3. Most severe service conditions for room locations as listed in w.F D. Telecen betmeen E. Crandall (PSEAG) and attached sheets are shanes in "Speciffed* celian. (huf4706

",. I Ed let11er (TOSAR) dated 3/5/85- (Qualified Life)

Ref.E.Pg.50)

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ATTACHNENT TO EESS NO. J301-T-002 Sh.1 of 4 TAG NO.

EDCATION FUNCTION NUREG-0580 RENARES IIten 2)

(Item 81 fItem 61 APPENDIX-E a.

CATEGORY 1-EG-FT-2549Al RB 102'. As.4309 Measures SACS pep discharge flew. Provides signal to main con-2a Mll-1 M/R Item 1.3 Model 32DP2 trol board for indication. R.B.1.97 requirement 1-EG-FT-254901 RB 102* he.4307 1-BC-FT-4435 RB 77', Am.4205 Provides signal for flow indication of remote shutdown. Panel Additional opera-M51-1 M/R Item 3.5 Model 32DP2 based on RHR flow to reactor vessel tor information and power sup-plied from Class IE bus 1-EC-FT-4649A88 RB 162'. ha.4608 Provides low pmp discharge alarm signal and control signal to 2a MS3-1 M/R lten 1.9 Model 32DP2 shutdown fuel cooling pump on low discharge flow 1-FC-FT-4158 RB 54'. ha.4108 Gnses RCIC pug discharge flow and provides control signal for 2a M49-1 M/R Item 1.17 Model 32DP2 RCIC pap turbine 1-KP-FT-6053A88 RB 102'. Am.4315 Provides a signal for alarm and indication and control of MSIV 2a M72-1 M/R Item 1.23 Model 32DP2 1.

inlet seal gas Ifne flow.

l-EG-FT-2511A88 RB 77'. An.4211 Measures RHR heat e:: changer discharge flow. Provides signal to Additional opera-M11-1 M/R Ites 1.27 Model 32DP2 nafn control room for indication.

tor info & power supplied from Class IE bus i

j 1-BC-FT-4461A RB 77' Am.4216 Provides signal for flow indication to control room based on 2a 451-1 M/R lien 1.29 Model 32DP2 flow to suppression pool spray header. R.G.1.97 requirement l-BC-FT-44618 RB 77'. he.4203 I

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i-BC-PT-4462R RB 77'. Rm4203 Provides signal for flow indication in control room based on RHR flow to drywell spray headers 451-1 M/R Ites 1.30 Model 32DP2

e I.TTACHNENT TO EESS NO.J301-T-002 Sh.2 of 4 TAG NO.

IDCATION PUNCTION (ttom 2)

(ttem 3)

NUREG-0500 REMARKS e-(Item 6)

APPENDIX-E CATEGORY 1-GU-FT-93944 RB 132' Am.4410 Provides control signal to FRV's recirculation fan on deluge

-93948 m 178', b.4617 la M3-1 WR lien 1.35 Model 32DP2 activation

-9394C M 132'. Am.4411

-93940 m 162' he.4615

-9394E M 162'. h.4614

-9394F Rs 178', Am.4615 f-GU-FT-9425A M RB 145' h.4511 Upon detection of deluge actuation, shuts down its correspond-ing FRV5 vent system fan 2a M4-1 M/R Item 1.36 Model 32DP2 1-EG-LT-250BCED. RB 201' Am.4706_

Located on expansion tank, indicates excessive loss of water 2a in one SACS loop starts the alternate cooling Icop Mll-1 WR ltas 2.11 Model 320P2 1-EC-LT-4661A RB 162'. Am.4605

1-EC-LT-46613 Provides low-low level alaru signal for skimmer surge tank and 2a control signal to shutdeum fuel pool cooling p g and close M53-1 WR ltas 2.15 Model 32DP2 filter dimineralizing system f solation valves 1-EA-PT-2356A1.

RB 77'. Am.4211 A2 & A3 Senses hfgh pmssure in SACS heat enchanger cooling water dis-2a charge Ifne to cooling teuer. Provides signal (two out of three M10-1 WR ltem 3.45 Model 320P2 requimd) to open dg valve to discharge to year if normal discharge Ifne is restricted 1-EA-PT-235481.

AB 77'. Am.4209 52 & 83 M10-1 M/R ltem 3.47 Model 32DP2 1-BD-PT-4303 RB 54' Rs. 4108 Neasure jockey ptump discharge pressure for alare Additional info M49-1 M/R Item 3.37 Hocel 32PG2 and indication to operator and q

power supp11ed fres Class IE bus 1-EC-PT-4669A RB 162' Am.4608 Provides low pump suction signal to shutdown fuel pool cooling 1-EC-PT-46698 Za MS3-1 M/R ltem 3.75 Model 32]PG2 pg e

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e ATTACHNENT TO EESS NO.J301-T-002 Sh.3 of 4 TAC MO.

LOCATION FUNCTION NUREG-058B REMARKS I

(Item 2)

(Item 8)

(Item 6)

APPENDIX-E CATEGORY 1-BJ-PT-4891 RB 17*. h.4219 Measures jockey pump discharge pressure and provides signal Additional info MW-1 M/R ltem 3.77 Model 32PG2 for alam and Indication.

to operator and power supplied i

from Class IE bus 1-KP-PT-5827A88 RB 102'. h.4315 Senses MSIV seal gas Itne pressure and provides signal for 2a M72-1 M/R Item 3.81 Model 32PG2 indication and control of MSIV system pressure differential control valve 1-EA-PDT-23734 RB102'. h.4309 Senses low cooling water differential pressure across SACS heat Additional Info M10-1 M/R Item 4.9 Model 32DP2 1-EA-PDT-2373B exchanger. Provides signal for alam on low service water to operator and cooling flow through heat exchanger power supplied from Class IE bus 1-EA-PDT-2354 A RB 102'. Am.4309 1-EA-PDT-2354B RB 102'. h.4307 M10-1 M/R Item 4.11 Model 32DP2 1-EG-PDT-2529R&B RB 162' h.460B Measure flow through fuel pool heat exchanger and inttfates Mll-1 M/R ltem 4.11: Model 32DP2 alam in control room 1-EG-FT-25 4 9B3 RB 102' Rm.4 307 Measures SACS Pump Discharge Flow.

Provides signal MI1-1 Model 32DP2 to Remote Shutdown Panel for indication.

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4 ATTACNNENT TO ESSS NO. J301-T-002 Sh.4 of 4 TAG NO.

tDCATION PUNCTION NukeG-050s asNARES (Item 2)

(Item g)

(Item 6)

APPENDIX-E CAT 900RT j

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1-GS-PT-4960A3 as 162' ha 4605 Senses drywell pressure qnd provides signal to recorder in 2a M42-1. IR Item 3.13. Model 120P2 contrul room. R.G.1.97 parameters l

1-ES-PT-496083 RB 102' Rn 4323 Senses appressicn chamber pressure and prwides signal to 2a M57-1, let Itan 3.13 Model 320P2 recorder in control room.

R.G.1.97 parameters.

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VES X ID sawus A. lechnical Spectf tcation 10855-J-359(Q).Rev.4

1. Stace the cabinets are in the reactor 614.

9 the louer para-4:0).WISs8CARLY TEBIED

3. (A&T Test Report 1035-1 Rev.t. (J-3590-41(1)-1) meters masent nector bW. m cM tf ans. Me W TES 1 IEF. A C.10855-J359(Q)-41(!)-2 higher values represent primary contalment LOCA parameters

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80 at the sample point.

D hechtel Deta Railiation Analysis CCN tit) 8 8 8"N 8029'aB44 Dtit 1/27/86.

2. All speCified parameters include margins of 15*f forlamp.101 E. 10855-J359(Q)-41(1)-3.

for gauge pressure.and *IOS for period of Elee equipment req'd to operate following a OtE.

ge F. Environmental Design Criteria 10855 D1.5, Rev. 4 92/H5)

3. Justification for t A heldity differences are shouse in i

Ref.C. Pg.2.(attached.

4. Aging toep. for specific components are shouse in Ref.B. Table 0-1.

5. Devices in attached sheets are mounted,on Panels IAC200 & IBC200 (Ra. 4bO2.4604)

w Bechtel Power Corporation Ref. C - Page 2 May 25, 1984 10855-J359(Q)-47(1)-2 l

6.

The analyzer output deviation you describe is noted post thermal aging and post radiation aging.

This variation in the analyzer output is to be expected when electronic components are exposed to the levels of accelerated temperature and radiation which exceed the worst case site specific calculated' levels.

'The important aspect to the qualification data shows that these accelerated exposure variations anneal out with time and the system returns to its normal analyzer output.

7.

The components located in Tables D-I and D-II did receive the radiation does indicated on the RSI Certificate shown in the Comsip, Inc. Test Report 1035-1.

8.

The containment pressure range required by the Specification J-359 is 0-62 psig.

The Comsip, Inc. maximum LOCA simulation test pressure was 70 psig which does envelope the required 62 psig.

IThe containment temperature of 340*F required by Specification J-359 is 40*F higher than the 300'F tested by Comsip, Inc.

This temperature difference would not affect the Comsip, Inc.

system due to the fact that all system components from the sample entry

bulkhead to the heated sample compartment are metallic.

The net

' affect on the system due to the 40'F temperature rise would be La decrease in the length of time-that.the heated sample compartment l

lheaterswouldstayenergizedtomaintaintheaverage275'Fsample itemperature.

---2'] affect the Comsip, Inc.The 340*F sample temperature will nct adversely system.

The Post-LOCA environment for the K-III/K-IV qualification tests calls for 90 5% R.H.

The actual test was run at a minimum

of 90 1 5% R.H.

The testing was physically accomplished as ifollows:

A4

-KW boiler continuously fed st'eam at atmospheric i

pressure to the chamber at a 4 KW rate.

Since this would rapidly l

cause the chamber temperature to exceed the 150'F, a large area condenser and multiple fans were used to remove heat and maintain the chamber isothermal.

The refrigeration system to the condenser and other surfaces are drained by gravity from the chamber.

The recording equipment was inadequate to accurately record close to 100% R.H.

Therefore, the record will not show 100% R.H. although there was a continuous fog and rain inside the chamber.

9.

Please refer to-the Comsip, Inc. response noted in above Item #8.

The Table F-I pressures are in gauge pressure.

10.

Please refer to Bechtel letter dated January 25, 1983 for clari-fication on the i

180 day versus the 100 day test duration.

EESS 030 2

1

=-M? h h

&4

--. a -

w. -.. -..

I Prepared by I dag DATE_.3884 W

• i Reviewed by d,(M,

ATE L/lo[b

\\)

~'

I tgjeJil' PENT IVAIJfATI(N 2329WIY 23tt.'l r o31 gg g,g gg ggggg; gg.ATitDe

'3ff'. Mb U g VAR-002 Hy/02 HEAT TRACE SYSTEM sov. Nu t~

IUllifvepfl*

f7Nif09fNt*

gyggy,

_)f 4 fyA (KX15GNTMrteN ff'll:ff78W It:X1ttlTitN PAftMGM3tS SPtrIFIID OtlARElifD SPfflFifD GIAl.lFlfD fCI18 0 USAI.lF.

t arf)#

ITIMI PtAf0lN OPEllATIMI e. C Test HINAfGCS (1) SYSlg Containment .pggg. too days 100 daye Ref A I2) TM M). fable 7.1 6 and Atmcspheric Control None Arrhenius calculation used tr, ar 5 Analysis Adequate extend thermal aging data. Tl)@. (*F) 131*r 146*r Ref. B Re f. C7*hl* 7 -'I Adequate margin Is provided by IC-C-200 Test excess temperature, ID-C-200 yau. 6 pygs3;gE pe! A ft s p_ _and Analysis None 17*r III UMMNT (PSIA) Atmos. A t n~h. pef.C.Sec.12 Hy/Oy Heat Trace Table 6 6 Par. 7.10 Test None 4dequate temperature. System 6 8VE I43 ftAfilFALT)lfit igellt)lTY (t) 1004 988 ,,g, g ,,g, e p 4,3,y Par. 7.10 Test None Not Note $3 __IPg. 198 pg pg g g), N/A N/A N/A N/A N/A None Not Required 10-0819-82-514D (6) 10-1286-83-404D ltADIAtl(M 3.4E4RG SE4RG Ref. E Ref. C Required FUGCTI(N ll4AfEj 1.!EbRB pef. B Table 7.1 Test. None 1.WG The heating cable is aged to See Note il Table 6 Note 82 IMin I 2.27E8NG which envelops t,oth $II E JEACY 40 years 5 years Ref. A Ref, D Camma & Beta specified dose s M IP83 aI M ELFIN _u/a @ 84*F S 84*P Para. 4.1 Appendix 8, Replacement of entire heat trace Not

83) ALTlAls N/A

• g*

Par. 5.3 and Required s e ystem in curretW required at 5 year Analyals atedotevals (H) R&ATI(N Reactor SFl4AY tref & T.C, Sec.8 I _ee 4 a N/A N/A N/A N/A N/A Hualding Ras 04602.64604 Not (9) AfRWE filID IJVIL None Required IXIIDENFATHW fGEf3EM'Et D 1. E A. TechnicalSpecifiNion MylTS IO855-J-359(QB (10) SE!9ERCAll.T 1TS!?D Rev. 6, dated 8/84. 1. Provides heating of the sample lines of the H /Oy monitoring analyzer yg3 ggg., n. Environmental Deisgn Criteria lO855-D7.5 NUREC 0588 Appendix E Category 2a. system. 2 W - Rev. 2 dated 10/84. 2. Bechtel Beta Radiation Analysis, CCN9 0295844 dtd 1/27/86. C. Southwest 3. (11) SRJIWElllAIG 1900. Researrh Institute Report Humidity is considered relatively instqnificant 8 SNRI-8904-001 Rev. 1, dated 12/85. Energiaation (Ref. D, Para 5.3.31 will since the Heat of the surrounding ambient raise internal air temperature above D. Southwest Research Institute Test Plan 4. Dimetalle heat temperature ef f ectively reducing relative humidit y. No 06-3647 Rev. I dated 12/18485. sensors elements shown on attached sheet sensitive. See Ref. F. are not age M-57-1 5. Temperature rise included t,y vendor. See re f. D. par. 5.3.3. E. Bechtet memo D. Dexheimer to K. Burrowes dated 4/10/85 - calculation of Camma Dose in Rooms 4602 and 4604. ID F. GE Document NEDF-30143 Page 2-11. e*

e .T Date 3// 76 Prepared By kiDb '^ d. Date Reviewed By .y I as I gggslegeper t3rAganNFItse ta891mftf 8982.T Str. OED: E g-ag-00g DAPA = GA loss CMAsesta DETBCTOR (pD23)

1. • O b

gg.pg; WIM G3G.R4 rips 3 SFNF1430 I 3 #IN B WBNBSEBir 4EX33GBftsurlate ge3tsegall 08Al.8 F. arms 8EB88F8E3'r 851018rT50s PAflage1. tsiS SrtE'IFllB Guessiles SrECIFIED gaAI.lF8tB se. uss 31tsgi pendE;8se gestmIES l '*** **d

• • reti a of no meeq=* ace a5 e-orauurses set. A ac t. o unne adequate a33.;VSTEst Process tges; pg. 20 A**IY

"" *T" " * * * *

• 89'
• 8 * ** * *
• f',d.

I" N* mediation saunitoring 390*F maf. A saf. C Test and (2) TN' 00. M. (*r) g40** 83 me. 20 Anneadia-9 amanvata mone 50,y 1-SF-ma 4825 A6s "*'* C pergsmaar 62 PSto 77 PSto aef. A nome ISPSto AePeadis-9 Aa*Iysis (3) amWoepfr (rssa) note e2 pg. 20 ION-Chamber Detector MEJFIVE met. A pef. C Test and mene Isot 1004 1004 (4) p W e TAC 10eIn:3 Its50tTr I4) Pg. 20 Appendie-9 Ana1yeie sequ! red GA (SoaRBafTO ELaCToC:lICS) thE Ehg8E*/ Ilot (5) IEEMI. OE). GM M/A N/A N/A g/A N/A Ilone Required 1000 ChaelierI GA:3023 sof. o Test a.4 5.Is7mc note es m.f. a seess are Radioactivity RAD 8mtl(pg Ref. C Pg.4 Analysis Adequate Ml Mascritas g anggg Note se asone 34 Table g Ref. g teote 86 at Test and 40 years Isote 03 met. A met. D unae Not UI MN 88'* llc y g50*r pg. 22 sequired al M BFIEIBentste f5 t>) N 82.Sa/hr* Test and anot Cheetcal Mme (S) IIMW5(BI meactor Senar N/A N/A N/A g,,gy,g, ,,qngr,d Ridg. Sm64220,4221 (9) AENE fldMED IEWEI. EEKISEBff3fflG8 SEFUEBEY: ggggg A. Tech Spec 10955-J3731Q) mov 2 dtd 12/31/05. g, g g 2. For actual pressure profile, see set. C, Appendie 9. (10) *E SECAALY a. Environmental Design Criteria IO8SS-D7.5 dtd 12/6/05. y g C. CA Report OJ373tgi-28-1 (s-254-960) g D.. Telecos./ dtd 3/7/86 From S. Lewis (CA) to PSB60 9.SEsam ( Airlsormel specified, 6.7E8am GPlate Out B opecified. 4. D. Canguly providing supporting Info regasding aging For meta Qualsfication, See Ref. g. (Ill SME3IJJWKE 14N3. of eD-2 5 congenent. oG 2 over the range ygg a gy* meta Qualit acation soport CCN00291911 dtd 11/15/84. S. 204,overall, system accuracy within a f actor E. pef. A Pg. 54. seemeure up to IE7 MAD /Nr Caema radiation within enesgy f rom 60stv to ~ 6. $4.Z4-l 1 serv and psovide output to class It recorder s shall also have dan 6837 and recording in Coatrol moos n.c. l.e7 requi r ement musesoses Cas.aa.

Prepared by .T. Mg Da t e _ 3/4/84. y-o i Reviewed by d.lM. k Date 3[lBf8/4 V DI EQUIPfeNT EVALUMIN SJPMARY SiEl.T 9er. No: J601-25-002 IOPE 04:EX QNERMING STATION NAMCO LIMIT SWITCH RW. NO: 3 IytrEs 3/6/n6 INVilOSGNT UOQSSWFMIN IEITJENCE ~ EJUIPPENr GJALIP. OPtN DESCRIPTIm PARAfET D 6 SPECIFIED QUAL #IIED SPECIFIED QUALIFIED ft.10D ITtP6 MAK;IN ItMAfg(S OPERMING Ref.C Ref.A Test and (1) SYSt1M BC FC.FD Tift: 100 days 134 day Pg.81 Fig 13,P.7-8 Analysis None 34 days by analysis-Ref.8 30 aay teIT~ extended SEE ATTACHED SHEET @) TM IO. TDF. (,F) suu t-Junin .nu t - > J/ g ner.c wer.a 148'F-100 day 200*F-25 days Pg.42 Fig.13 P.7-8 Test None 40*F Note #3 & 4 u.,,,,, re a zu SEE ATTACHED $HEET PREssusE 1.5psig-30m 80psig-5 3/4 (M megCNENT (PSIA) Opsig-100da 10psig-25 day Test None 18.5pstg REIJtr!VE 100%-6 hrs 100% Water (4) feNUFACIURER tamuDI1Y (t) 951-100 days Spray Test None Not req'd Note #3 Room #4110 a gy p N/A N/A N/A N/A N/A None Not req'd EA180-32302 pagggg 5.06E6 RG 2.04E8 RG Ref.C Ref.A (6) ilmeCTION (RAOS) 1.WOI Note il Pg.42,81 Pg.4-9,10-15 Test None 1.94E8 RG tote #3 Room #4110 SEE ATTACHED SHEET 40 rs see pet 2 Ref.C R A Test and Periodic Maint. Reg'd Main (1) ACmeACY MItc 79 Pg.42,43 Pg.4-7 d[12 Analysis None Not req'd Instruction EA189-90050 & i a) SPECIFIED N/A Not 3' NotTl2 b) ACIUAA. N/A Rm. 4111) 90051 of Ref.B provide Main, schedule. Chemical and Ref.A ' (d) LDCMI m REACTOR SPRAY N/A water spray N/A Figure 13 Test Mone Not req'd BLDG. 5EE ATTACH.$H. Pa.7-8 (9) A80VE EtD0D ILVEL DOCtMWFATION

REFERENCE:

YES 3 80 lettS A. NAMCO Qualification Report

1. Beta radiation qualification report. CCNf0264399 dt,5/15/84.

(10) SEISMICA11Y TESrED 08 3 Q- . wl s si f one g es aH led yrs @55'C (Ref.A YES X g3 - IEP. A Fig.8 & EA189-90051) Switches with N8R-Accobest gaskets qualified

8. Arrhenius calculation to extend DBE test time, for 4 yrs 940'C (Ref. A. Pg.EQ-II EQ-12)

(11) SUIR/E!!MNCE 1E00. EQPM #421 (part 4 of 4) DTD. 6/1/82 (J605).

3. Most severe conditions for room locations as listed in attacecJ sheet are shown in "Specified* column.

MO O e 08 ble #6

4. The i

a s are conservative. For Actual Test Profile

O Prepared by J. Alar. Date J/#/dT. 4 V I / Reviewed by._ btb.kQht Date _3./fo/A4 I IUJtPeeNT IMAlptrim SMWWEY SfEE.T OOPE OtDX GNERNFING STATIN ASCO SOLENOID VALVE P my, 3 03 P301-SV-001 fl -{ NN. 8808 ' I '~ ' DHrg-g/g4 SQlJIPPWWF ENVIfpegNr 00C199Nr# rim EfEI68& FTERIPrIU4 PARAfETERS SPSCIFIED QUAfIIIED SPECIFitD QUA1.IFI m ft:INUD I196 MAICIN IngWg(S OlAI.IF. OPEN I' wer.nas Ner.L rest and (t) SYSIDt EC.E E.EG.KH 100 days 2000 days See Sheet f2 in 1 F .1 Analysis Mone >2000 days by analysis, Ref. D 30 day test extended e23.rm m. 'Inc.. (*F) 39u t/Ihr 345 F-3 hrs See Sheet #2 150*F/100da 265*F-30 days Test .7pa transient during 08E paessyg 20psig/thr 30psig-5 days None 4dequate I (1) (Dre30NENT (PSIA) 0.3psig/100 24psfg-30 days 10psig provides adequate margin Note f4 SOLEN 0ID VALVE d8Y5 Test None d U RHJtrIVE 1001-6hr 1001 Note #4 (4) MANUFACIUllER Ref.C l ASCO iSJPtIDITY (4) 901-100 days Steam 4 Spray Figure 4.1 Test None Not req'd 23 days U 14.2.3 Flo0DifC/ (5) terEL m. FRoly N/A N/A N/A N/A N/A M*n*- NP-8320A185V 4 Not req'd ) RADIATIOg 2ETR G 2.0E7R G and Re f.E.Re f. Ref.C ,6) EtJNCTIN .1 1 (RADS) (sh.f4102) 2.05E8R G 148. App.I 14.1.484.2.2 Test N 8 See Notes See Sheet #2 1E7R G Notes l&2 ' 11.8 1 'in D

1. 3,3,6 40 years 8 years Ref. E Ref.C Note #3 D) m Actec 104 *F 9140*F lote #5 Appendix C 8 Test and None Not req'd Report. Provides a) SPeCiritD N/A

~ appendix s. or the Ref.C 20K cycles 14.1.1 Analysis b) ACIUAI. N/A ' Guidelines. Periodic Water spray Ref.C 4a in t. Reg 'd, L(1) (DCMrIGs REACTOR SPRAY 'N/A 29 days i BUILDING -Sheet #2 afg Figure 4.1 Test None Not req'd (9) Aa0VE fl.ots tJNEL DottseNrATIGi IEFEllENCE: YES L NO _ A. Design Specification ~ 80tES

1. The

( t0) SEI9tICAIJ.Y 'IESTED 10855-P-301(Q),Rev.7 (11/81) lified Camma pose encompasses specified G&B doses.

8**

• I-G-

~ EF.C

8. Technical Speciffcation

2. Viton elastomer For further info YES X I

is quellfied to 2.0E7R G, ethylene propylene i ND ~ (14.1.W-- 10855-P-302(Q),Rev.4 (7/81) elastomer (EPDM) is quelf ffed to 2.05E981G (see NRC in #85-08), C 1811) SJHWEItJJeem 3E0D.. ASCO Qualification Report

3. The Viton elastomer on ASCO valves in Ibs.4102 ($V-4676A,46768, AQR-67368/Rev.0 (3/82)

YES X IEF.C 4618 and 4663) have been replaced with ethylene propylene. t PO ] App.CI (10855-P301(Q)-543-1 and 543(2)-1) D Arrhenius calculations for

4. The qualified data shown are conservative. For actual qualified'

exten, M-53-1.M-II.M-57-1 ston D8E test time. EQPN #364 Temp. and Pressure Profile see Ref.C. Fig.4.I.

j dated 5/3/82. E. Environmental Design criteria

5. Worst condition considered (fhe 4101).

F. Ililler Report 10855-07.5, Rev.2 (10/84) SER-St-200-P lP301-533(2)-1) C. Beta Qualification Report.

i Prepared By T A7 Date 3/8/r6 ~ u [ Reviewed By b.h. klofSG Date G I 4 1 f_ b IG83Mefr WAAAA4 PION :Asseuty testa.T M M MenarleG WWIdas tlNIIORQUE A.C. IEDTOR OPERAIOR 1 3Ber. Nos P302-M-003 [ W. ses 4 -- 8EE8 _3/8/86 Isn'nameWsP

====warnas marr==nr

• TeGs FAsuesnus specarse gansssim spectrs m cuna.srssa WEmerseR3 R e Ap L

83) Stragge VARIOUS TleE 100 days 130 days -

Pg.1 p 3 p 3 p.ps,36.3-{ i 30 days 118E test eatended g .nce Ameca..J sheets. Note 65 31 Test & Analysts mone y analysis. Ref.E. (2) w so. SEE top. gar) B-rgs.3-3 ATTAC8E8 $NEETS See note #1 See note #2 s.l.3 3.0 gest i sleet provides j pt ang jlp'"qAj r,g, 4 ua e ym s-rys.J-s OI GBWWWfr (fess) See isote #1 See slote #2 0 - 3.3-3 g AC ISTS frERAIGR Adequate (gig amJrste 1005 1005 1 te) aangRaracama assaagTV (4) g-Pg.3-3 LiittleglE Not req'd runnmaasru

45) seas.30.(VARIOUS) runs N/A N/A N/A N/A N/A Note #4 588-$ FRIES mad 8Ar$GO i

8 5.Inl0 RG 2.04:10 RG "* APP I E (6) MAICTE(he (theS) Ps'.EQ-ilo g I.5 ale SEE ATTAcado SidETS ,g,3 4 as note si 118

• m.r. y Test 40 yrs 9 10 yrs 9 A. App.!

B.Pg.3 and Test 5 Analysis gy) arnsment. actas; 150*f - 150*F Pg.1-3 Add'*d'se A 10*C Rule ,.sw k m in esence req'd a) W W' Bel m N/A Not req'I per meintenance manual b) ACE 2AR. II/A Pg.5 E o iner.itsu

g. 913.3 IS) taCA5908 Sreat N/A N/A SEE ATTACleED LIST Pg. 5 Test m er (9) Amme fEsm 825.

Na mI to A. Tech 3Pec FJung) New.4/ Design Spec. P301/P302(Q) soms #1 Ilsg igsgo ar pegs $, p$gg ~ ~ m

s. Lsestergo. Report 600316A. Rev.s Rev.7 (11/81) 0-20 sec 340 0-62 g ~g gy, 3 (P301 & P302(Q)-133-6) 20s-5 esa 340 62 Se-3 nr 340 40

~~~ as C. Lielt. Apt.fe0llg. 7/82 #B005S 1/11/60 3h-6 hr 320 40

3. Qualifled mad.,

~ PS-300/P301(Q)-133(4)-1. P30l(Q)-133(2)-1, 64 24 hr 250 25 Dese encamp.sses (11) SWfEI8AA8G 845. M ' ** L O. Llelt. Apt.ft0021. Rev.A 1c/18/18 days 200 (Sec.4.0 Pg.6) m doses (2.5a10 rat 0Y ~ E. L imi toryARRH-001. Rev. t. Dt. 8/12/85 82 0-6 hrs 340 105 ,'b. Pp 6 F. Bechtel Seta Rad. Qualif. Report. 6 hr FF g g G. Olis 10855-01.5 Rev.2 44.4e days too le

I i Prepared by .I. A/ae Date _.if4'/F6 7 Reviewed by d,.lN. h k Date E/10/& y 13 4 soumeur== arias ma==r War = r. m. P g.15 00s saart Guzy twommernac arusons llAMCO LIMIT SWITCH am. ame e SWEs 3/6/as BRflEBOWfe GMX25GNwlGI N V e4Jutpoener l 8*Srh8PTIGe PARADEWEM SE*8FIS SIAiElim SPECIFim Ot4AE.8FIED

1. ElTIIDD 3733 3 smaG33g gg*

@nt.g r. orage oygngagg 100 days Re f. A Ref.8 (1) SYSTet TIM 9200*F 134 day 5 Appendix 1 Fig.13 P.7-8 Test and 30 days DOE Test i SEE SHEET ATTACHED 11.B. 3 kr r Ama = h extended by Ref. C h va 128 tac so. W. ( FI 340-3 hrs E5~3/4E7 tet.B ma-- 2nd transient during D8E Note # 2 Note # 3 Fig.13 P.7-8 Test None None SEE SHEET ATTACHED er-s ein 50-5 3/gnr m provides accept. margine I eil ameGmer (petG) Note #2 Note #3 Test None 18 LIMIT SWITCH g yg 1005 1001 (Water Spray Test None Ilot req'd del aseen (t) y N/A N/A N/A N/A N/A iA180-31302 None Not req'd 24-180-32302 "*"8'IG8 5.lEFA G 2.04ESR G Ref.A Re f.B ttl stascTsas temest note es note es MI" I Pg8-4.,10-15 Test None 1.5X8A G SEE SHEET ATTACHED 40 years 2y r ee l so.",- Ref.B Test and Periodic Helat. Req'd (76 mm AGlaC II syree 31., Pa. 4-7.E0-12 Analysts None Not req'd Malat. instructions EAltl9-al spectrEED N/A lete #1 90050 4 90051 of Ref.s pro-td ACitang, N/A videt malet. schedule Chemical and Ref. t Ref.S l ggg ggyaygag .wsug YES Water Spray p,19,23 Fg1 Test None g stE SHEET ATTACHED ^ Not req'd IS) asERfB BRAXle ImgL ODG8WIIIurtfas serumansts g i M.L 80 A. Design Specification

1. Qualtfled Life is 2 yre e aso*e s yre enin*r for stem. uese, eaticone cover (NOT SPECIFIED) 10855-P-30l(Q). Rev. r its/ sty.

se por t,teoan from o, ces of m, ris. e a mate,-soest. go.a 4toI N " 1Est e g y agr. g

5. IBA8eC0 Qualtffeation Report g

g QTR 105. Rev.4. Dtd. 1/84 20055-P30l(Q)-228-2 & 1%-7)

2. The specified data shoun is conservative. For actual specified temperature till 8R8'8E8N 8EGB-C. Arrnentus calculation to extend and pressure profile, see Ref. A. Appendix 1.11.8.3.

1EE 13EF. 8 DSE test time to 100 days.

3. The quellffed data shown is conservative. For actual qualtited teoperature 88 _

EQPM d421 (Part 4 of 4) 6/1/82. I and pressure profile, see Ref. B. Fig.13. Pg. 7-8. D. 8echtel Seta Qualification Report

4. Quatified rediettoe dose encompasses specified gamme plue Newtron T:02.5c7 meds.nes.gL E. Environmental Design Criteria f oEer d a

-10655-D7.5, Rev. 2 (10/84) 5, 9.stans fairkereet leefde drywest s. s se,as t at sborne ) le meector suilding: met.o for c Date Quantfloettee. See set. D. k

e e o P 9 ATTAOeOT TD FESS NO. PW-HV-003 Note f 4. l.AE-HV-F039 is not qualtfled for submergence caused by a feedwater line break in the steam tunnel. It has been j provided with primary and backup IE bus protective devices located in hazard free area.

5. The required operability time of 1-BC-hV-F009 with magnesium rotor,is first seven days after an accidnet. The operator is qualified to meet i

this condition, Ref. H. Furthermore, the power supply for the valve operator is protected with double breakers,-with contactors or.an with the valve in the open or closed position. 4 4 Doc. Ref. II. GE Inf ormat ion let ter SIL 6 425 did 7[17/85. t

Prepared By L Nag Date J45Arg Q-i e Reviewed BY._ 6. Date 18/ble v 155A EUJIP9ENT INAIMtFIG8 3#9thftY SitTF 8N OE2R Q3EHAFIPC STATIM ROSEMOUNT 11538 TRANSNITTERS UTIL121NG OUTPUT Sff. 00 II9812-IN17- 001 I CODE =R= stECTRONIC CIRCUIT 30ARDS SE. 98): V 3 [MFEt J/5/86 IUtIIPPEBff IBWIfG OW3ff 000SE3ftstflas IEftlesem 11ESOtIPTIG8 PAftpfEFEI6 SPECIFIED Ouaistsen SPectFIED asaAt.srs fD tenttu) 31us penJctw sv>tafas 0)Al.IF. OPfte ma.. ai g ggg; III SYSITDI Ref. A Ref. C Test TifE 100 days lit days Appendia N Arrhenius calculation used to este Fig. I and See EESS$155 (2) TWC 80. 9 P9-None 878 DBE Test data to envelope post D8 Raf. E Analvais 1139. (*F) 148'r 265'Finau) Ref. C peri d (Ref. El

• *A See Notes 4 and 5

,I* I11 I Adequte PfhMEM 3 (30 min) 24psig of. A Test _.None Margin provided in operating time. (1) GDE U Efff (PSl4 O(180dayel Pg. 42 Ref. C Electronic circuit ylg. 1 Test None 21paig Ref. D identifies more conservativ boards (output code R) M VE (Atmos.) DbE specified conditions. (4) FW84JFACitJOEft DEsg()(TV (t) 100% Ref. D Ref.8,Pg.26 Test None 1004 APP Im J "* I ' #' 'I9'I Nog Saturated steam used in DBE char go.. oung (Spray) Table 6 g FtamtuW IS) PEMER. 80 f1U918 N/A N/A N/A N/A N/A None ANP.-P/N!!53-0125-0002 Calib.-P/NII53-0231-0001 IIADIAftG8 6.lE6RG 2.4437RG p9gg,{ Ref.8, Table 8

80) FISE'TIOf IRAf5) 1.lE6RB Note $2 Imporved electronics fo.

Table 6 !.8E7RG the 11533 series (Nogeg 4 40 years 17.8-20 years Ref. O Ref. A Test (7) ACQJRACY

1. CIDC 0 10l*F 0 104*F Telete 6 Pg. 66 and None al SPEElFlfD 10.25g Nog Complete replacement of A& 3 A& 8 Analysis Required transmitter required at end of b) ACTtJAL

<g (See Note #3 3 qualified life see (EESS 8155) Nater (S) IIX'AFIGd SPHAY N/A Spray N/A Test Not

• *U See Notes 4 & 5

"' h ^" " 1

19) ANWE FlHM 12.VE2.

IKXISE3fFATIOf IEFt3EDsI '9"I' TES I 90 _ A. GE Co. Equipment Qualification Report m 1. NEDC-30446, Rev. 3 dtd 11/21/85 (NSSS Book Improved electronics used in the 1154 series transmitters were designed by Rose-(10) *EI95NY 1TSTED No. C59_ See EEsSel55). mount to be f ully interchangable with the 11538 transmitter. These new *trcuit 1 boards designated as output Code "R*. have been qualified by similarity and pg B Rosemount Environmental Qualification type 8uPPlemental Det testing for use in the 1153 transmitter as reported in Ref ~ I8

• gy test report (D8300131 Rev. A dtd 12/13/83).

. sec. This document summarises qualification data for the new electronic circuit (II) NIEN 6. C. Rosemount Environmental Qualification type presenM in Rd. E and c@Wnu W Wk hmnt IM MestmwWW be3*d5 YES X 3EF. A test procedure (3825, Rev. D, dtd 4/8/92). qualification of Def. A (NSSS Book 8C)9). D Environmental Design Criteria 10855-D7.5 2. 5 0 and !!48 Rev. 4 dtd 12/85. Qualified / test radiation dose envelopes both specified gamma and beta equivale nt I*I'*

i. Arrhenius calculation.119812-ARRH-001 3.

A separate setpoint methodology program will evaluate post DBE changes in ac. u ,dtd 12/85.

~ e ATTACHMENT TO EESS NO Il9812-XNIT-001 NOTES (Cont'd!

4. The following Rosemount by PSE&G as replacements for the original'll53B transmitters supplied by and qualified b1153B transmitters with "R" electroinc circuit boards were purchased' NSSS Phase III and ATWS Program. See EESS No.

y CE Co. under Appendix E Category, P&ID Reference, 155,110, and 114 for location, function, NUREG C58v and further information regarding specified and quallfled parameters. Tag No. M Tag No. My 1 BB FT N014A B31 1 BJ LT 4805-2 BOP 1 BB FT N0140 B31 1 EG PDT 2485A BOP 1 BB LT N080A B21 1 EG PDT 2485B BOP 1 BB LT N091A B21 1 EG PDT 24R5C BOP 1 BB PT N078A B21 1 FC PT N058D ESI 1 BB PT N090A B21 1 FD PT NOSSA E41 1 BB PT N090P B21 1 FD PT N055C E41 l 1 BC FT N052A Ell 1 FD PT N055G E41 1 BC PT N058B Ell 1 FD PT N058G E41 1 BC PT N058D El1 1 SS LT N091C B21 1 BC PT N055D Ell 1 SB LT N091H B21 1 BD PT N05) E51 1 SN LT N08IA B21 1 BE PDTN056 E21-1 SN LT N001B B21 1 BE PT N054A E21 1 BB PT N403A B21 1 BE PT N054B E21 1 BB PT N403E B21 1 BE PT N090N B21 1 BB LT N402A B21 1 BE PT NC90P B21 1 BB LT N402E B21 I 1 BG FT NO36D G33 1 AB PDT N086A B21 i e '4 4 6 G 0 a

9 ~ ~ ATTACHNENT TO EESS NO. 5. The following Rosemount 1153B transmitters with output code "R" electroinc circuit board was purchased by PSEEG for replacement of the original Tobar transmitter. TAG r>*. LOCATION PUNCTION NUREG-0588 RENARKS IIte m /) (Item 8) (Item 6) APPENDIX-E CATEGORY l-b5-PT-4771 RB 54' RM 4112 benses pump discharge header pressure and provides Additional infc M55-1 PO ltem I signal for indication and alarm. to operator and P.O. 16701-004-1076 power supplied from Class IE bus. 1-EG-LT-2508 AED RB 201' RM 4706 Located on expansion tank, indicates excessive loss 2a M11-1 P.O. 132016 of water in one SACS loop, starts the alternate cooling loop. 1-EG-PT-2544 A&B RB 102'RN.4309 Measures flow in SACS loop and starts back up pump 2a Mll-1 P.O. 132016 CED in alternate loop on low flow. 1-BC-PT-4462A RB 102' RM4328 Provides signal for flow indication in control room 2a M51-1 P.O. 132016 based on RHR flow to drywell spray headers. R.G. 1.97 Parameter.

f i Prepared By I A/e/ Date,9/4/g6 (/ ' / Reviewed By O.N. Date D[lO[86 u I ms I EUJIPfEBer EVALAJNrim SmetWW StEE.T HOPE GEIN G3dEJutrito Srets HUMIDITY TRANSMITTING SYSTEM S r. NO: M780A.HT-012 BE.V. 00 7 DNrts 1/i> /81 ISIIME3rr Epefilesert 000sestrarts IEFElessa OdEOt!PTim PAAAPE"ITJG SPECIFIED GJAEXI!ED SrgCIFIED QUALIFIED Pt."ItE]D 1113 6 ftAICD4 SDgusts GJALIF. OPitt gg 100 days 100 days Ref. A Ref.C Test and Mone Adequate Adequate mergin provided in gg g App.8 Tab 48 Analys1s FRV5 temp. (2) TAG ND. VEar. (*F) 148'F >l80*F SEE ATTACHED SHEET Test None >32*F Plassugg (3) WpWOdDer (PS$ ) 0 0 Ref.C Excess Temp. margin Pg.31 Test gone Adequate provided. {TYTRANSMITTING g ger,c,p s, (4) peuerActuaEn es#GDITY (%) 1001 801 g 12-15. Table Test tone a WTM 48&Pa.54 Not req'd Noto #2 FID0 Diag / g$p pt)EMI.90. FRDIN N/A N/A N/A N/A N/A Mone Not req'd DWG.fl023-55667-33 (REF. A. TABLE 2) RADIArtm 243E6 RG Ref.B Ref.C.Tble 1

16) nim (RAss) 1.lE6 RB

>2.2E6 RG Iable#6 App.IV and Test gone ).17E6 RG Note #1 E ATTAND SHEET 40 years 40 years Ref. A. N C. Test and (7) arvi g Actic 9100*F 9123*F App.8,Ref.8 Pgs.38-42 Analysis None Not req'd at 5 year intervals' a) MIFIEEs fl1 MA. Gasket replacement required b) Actual M Table #6 & Table 44 (Ref.A. Pg.9) (Pg. A .1) ggy N/A N/A N/A N/A N/A ~ SEE ATTACHED SHEET None Not req'd

19) Aa0WE FImma (EVE 2.

D00stDiraftas antapsCE: YES L 80 A. Technical Spectfication NDIES ) 7

1. Beta Qualtitcation Report M180A.

I (10) SEISWCALLY 1ESTED 10855-M760A(Q) Rev. 14. Dtd~5/85 2. Setpoint of the equipment is 65% R.H. t o maintain less than 70% H.H. YES I EEF. C

8. Environmental Design Criteria 80 10855-7.5. Rev.2. Dtd.10/84.

C. Nuthern Qualtftcation Report (11) sammIILAsem 85100, 8PS-1449. Rev.2. Dtd.4/26/85. Yts X IEF. _ C (10855-M180A(Q)-205-2 and -1) 80 _ M-83-1. M-84-1 e

I NOGS PSAR 3/86 TABLE 3.!!-S p.g. gg og 319 EQUIPMENT SELECTED FOR MAR 8N ENVIPONNENT QUALIFICATION SYSitMs SAFETY AUX Cta)L SYSTLN P6lD F4 N-i!-1 I D m). PAN TNI ACTION P.O. Note (St MP1 NO. COMPON t:NT 14 CATION EQUIP. Pl.AN EQUIP. SLDG. ELEV. NOTE (Il NOTE 82) ES$$ REP. 10 0 Mool 1 -EG-P lyt-2 4 8 S A Muul 3-EG-PDT-248 Sit Ditt. Press Tr ana. Reactor 102 No No ISS,lSSA p N'8 0 8 l -EG-P trt-2 4 8 SC Diff. Presa Trans. Reactor 102 No No 155,855A f MuGI l-EG-FDT-24sSD Dif f. Press Tr ana. Reactor 102 No No ISS,lSSA ~( JJulo I-EG-NS-24GSA2 Diff. Press Trana. Reactor 102 No No ISS 'l J20lO l-EG-HS-240$N2 Hand Switch Reactor 102 880 No 25 e Hand Switch .sJolo 1-EG-HS-248SC2 Reactor 102 No No 25 '4*w ' Hand Sultch JJulo I-EG-HS-248SD2 Reactor 102 No No 25 Hand Swltch P90SO l-EG-HV-249tA Reactor 102 No No 25 Contr. Valve P90SO l-EG-IS-249tA Reactor 102 No No 144 Limit Switch P30SO l-EG-HV-24988 Reactor 102 No leo 144 Conte. Valve PIOSO l-EG-3S-249ta Reactor 102 No No 144 Limit switch P30SQ 4-EG-HV*2494A Reactor 102 No 16 0 144 Contr. Valve Pl0SO l-EG-33-2494A Reactor 102 No No see PROSO l-EG-NV-24948 Limit Sultch Reactor 102 No No 144 Contr. Valve P30SO l-EG-33-24948 Reactor 102 No No 144 Limit switch P3050 1-EG-HV-2496A Reactor 102 No No 144 Cont r. Valve PROSO l-EG-3S-2496A Reactor 102 No No 144 i Limit Switch P1050 1-EG-HV-24968 Reactor 102 No No 144 Contr. Valve PSOSO l-EG-IS-24968 Reactor 102 No No 144 Limit Switch PloSo I-EG-HV-2496C Reactor 102 00 0 No 144 Contr. Valve P90So I-EG-IS-2496C Reactor 102 No No 144 Limit Switch P30SO l-EG-HV-24960 Reactor 102 eso No 144 Contr. Valve PjoSQ I-EG-38-2496D Reactor 102 No No 144 Limit Switch 132916 1-EG-LT-250BA Reactor 102 Iso No 144 14wel Trane. 1 !!2046 l-EG-LT-2500s Reactor 201 seo No IS5A lavel Trana. J1010 1-EG-LT-250cc Reactor 201 soo eso 1554 lawel Trans. Reactor 20I eso No 29 J)98Q 1-EG-LT-25000 Level Trans. Reactor 201 seo No 29, 1 I t. 4 Amendment IS S = e I

3/86 l NCC3 P2,3 f oge 3 2 C f f l y ' TABLE 3.11-5 EQuirgENT SElJCTED POR HA98N ENVillONMENT QUALIFICATIOes P63D M-II-I .s y si t ee t S AF ETY AuE CouL SYSTEM fE PAN TMI ACTIOce I D No. IDCATIOel EQUIP. PLAN 80UIP. P.O. Note (51 MP t. eed. WMPONENT SLDG. ELEV. DeOT E (Il feOT E (21 EEES BSP. 80 0. P105Q I-EG-HV-2522C Control Valve Reactor 102 leo No 147 Plu50 1-EG-35-2522C Limit Switch Reactor 102 No No 147 PluSQ 1-EG-HV-2522D Control Velve Reactor 102 No No 147 Pe050 1-EG-35-25220 Limit Switch Deactor 102 leo No 147 r J 2010 1-EG-MS-2522DI Hand Switch 'Deactor 102 leo No 25 J2nl0 3-EG-PDT-2529A Press. Diff. Trans. Reactor 162 No No 29 31010 1 -EG-P DT-2 5 298 Press. Diff. Trans. Reactor 162 No No 29 e J55tQ 1 -EG-T E-25 35A Temp. Element Reactor 102 Vee No 4) J5560 1 -EG-T E-2 5158 Temp. Element Reactor 102 fee No 43 112086 l-EG-rT-2544A F.ow Trans. Re act or 102 No No ISSA IIJ014 1-EG-PT-25448 Flow Trans. Reactor 102 No No ISSA 512016 1-EG-FT-2544C Flow Trane. heactor 102 No No 155A I)20l6 l-EG-FT-2544D Flow Trane. Reactor 102 No No 155A 18010 1-EG-FT-2549Al Flow Trane. Reactor 102 Vee No 29 JeulQ 1-EG-FT-254951 Flow Trans. Reactor 102 Tee No 29 JIO10 1-EG-FT-254981 Flow Trane. Reactor 102 leo No 29 P1050 1-EG-HV-7924A Contr. Valve Reactor I62 No No 144 P9050 1 -EG-IS-11'2 8 A Limit Switch lheactor 862 No No 344 8'1050 l-EG-HV-79218 Contr. Valve Reactor 162 00 0 No 144 Plu50 I-EG-3S-7921R Lielt Switch Reactor 162 No Ng 144 P9050 1-EG-nV-7922A Contr. Valve perttor 162 No No 144 P9050 l-EG-35-1922A Limit Switch Reactor 162 leo No I '4 P9050 1-EG-HV-79229 Cont r. Valve ReaClur 162 18 0 No 144 e*lu50 1-EG-IS-79228 Limit Switch Reactor 162 No No 144 k Asaendmen t 45 I e i s

l 4035 PSAR TAeLa 3.ll-S 3/06 p'g. 34 og ggg kEhltM1AL NEnf REMOVAL SYSTEM EOultnsw? SELECTED POR NASSN 1NVlaONNENT QUALIFICATION SYSTEns PC P610 n-St-i ID MO. P.O. NOTE (S) PAM MPL NO. OlMPOcerNT 14CATIDes TNI ACTION EOulP. Pl.AN soulP. ~

SLfM3, ELEV.

NOTE (1) te0TE 12) 8888 SSP. 81 0 n001 5 -BC-P T-N0 564 E005 4 -hC-P T-N0 5 7 Press. Trans Ell Ell n001 l-BC-PT-NOSSA Prese. Trene. henctor 54 Ell too qual 1-sC-PT-MOSee Frees. Di f f. Tr ane, Reactor 77 No ISS sto [ Ell teactor 77 No 106 Hout 1-8C-PT-N058C Press. Diff. Trane, Ell see n0 +i l I-SC-PT-N0580 Press. Diff. Trane. heactor 17 No ISS Ell No d I-ac-POT-N060A Prese. Dif f. Trans. teactor 77 No noon Ell No ISS,lSSA mio n I-ac-FDT-N060a Frees. Di f f. Trane. henctor 77 No ISS . -. M, b,I' 'F

• ('g '

Ell Iso Fttl%9 l-BC-TE-N0274 Press. Diff. Trane. Reactor 77 No eso 155,1354 P448S9 I*BC-TR-N0278 Teep. 88ent. nesctor 17 No 106 No 4-JSS&Q I-8C-78-4401 Temp. 5 tent. Reactor 77 No 106 Tee 9 38010 3-sc-PT-445% Temp. Elset. Reactor 77 No 34 g Tee P 6080 1-sc-NV-4489 Plow Trans. Reactor 77 No 34 g No Ptolo I-8C-3S-4419 Control Valee Reactor 77 No 43 No .7 Jo lo I-SC-PT-446tA Limit Switch Desctor ?? No 29 leo J3010 1-SC-PT-44618 Flow Trane. teactor 77 No III No 132016 1-SC-PT-4462A Plow Trans. Reector 77 No 127 fee Jiolo 3-SC-PT-44625 Flow Trane. Reactor 77 No 29 Tee Plow Trans. Reactor 102 No 29 Yes Reactor 77 No ISSA l tes No 29 \\ l Am*8Minen t iS i g. a 6 e 4

1 e i ,i I i a 9 HCGS PS AR TAHLE 1.11-5 '*U* I NOTES (!! This column ident it tee the equipment located in a harsh environment required for post eCCident monitoring as defined in R.G.I.41 and FSAR Section 1.B.I.97.1.

82) Thee column identiften the equipment located in a harsh environment identified as TNI Action Plan Equipment as defined in NUN pG 0 7 3 7.

13) Itema that are generic are purchased and used throughout the plant and may be used in the Dg4 Harsh Environment. (4) Electric Penetration Assemblise for control and instrumentation circutte include inline splice connnector hite.

89) Limit or position evitch tag numbers have been created by using the '38' designator in lieu of the valve (HV)

~ designator f or purposes of equipment qualification accountability only. These tag numbers may not be f ound in P&ID's. echematice or the instrument indes. Enceptione to this occur when poettion owltches are mounted on manual valves or are under M001 INSSS) P.O. In trat case the tag numbers may be found in the instrument indes and applicable P&lD's. (6) Transmit ters with EESS Ref. No. 29 will be changed to Rosemount 11538 Transmitters utilising output code 'a* Electronte Ctreult naarde prior to initial criticality. Amendment 15 O}}