ML18041A080

Forwards Addl Response to IE Bulletin 79-01B Re Environ Qualification of Electrical Equipment.Containment Spray Piping Outside Primary Containment Is Main Shine Source

ML18041A080
Person / Time
Site:	Nine Mile Point
Issue date:	04/17/1980
From:	Lempges T NIAGARA MOHAWK POWER CORP.
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
IEB-79-01, IEB-79-1, NUDOCS 8005120208
Download: ML18041A080 (26)

Text

7 NlAGAR

'52 RO U MOHAWK g,o8'IAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474-1511 April 17, 1980 Mr. Boyce H. Grier Director United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Re: Docket No. 50-220 I.E. Bulletin 79-01B

Dear Mr. Grier:

Our letters of March 5 and March 28, 1980, transmitted partial responses to I.E. Bulletin 79-018. That Bulletin addresses environmental qualification of- electrical equipment.

The attached information responds to the remaining requests contained in the Bulletin. Discussion of previously outstanding items is also included.

Very truly yours, NIAGARA MOHAWK POWER CORPORATION I r~

Qt~7 ~ ~ ~ ~r ~1<

Thomas E. Lempges Vice President - Nuclear Generation DKG:jk Attachment

STATE OF NEW YORK )

COUNTY OF ONONDAGA ) ss:

THOMAS E. LEMPGES, being duly sworn, says:

I am Vice President, Nuclear Generation, of Niagara Mohawk Power Corporation. I have read the foregoing letter and the facts contained in the letter and attachment are true to the best of my knowledge, information and belief.

THOMAS E. LEMPGES Sworn to before me on this

<a~day of April, 1980 NOTARY PUBLIC CYNTHIA A. PETTA t:otcrv tonne tti tho stoto ot ciew Yoik Qostittod in Onondooo t.o. No. 4682225 My Contntission Exoitos Motcht 30, 19+5.

RESPONSE TO INSPECTION ANO ENFORCEMENT BULLETIN 79-018 APRIL 17, 1980

Provide a "master list" of all Engineered Safety Feature Systems (Plant Protection Systems) required to function under postulated accident conditions. Accident .conditions are defined as the LOCA/HELB inside containment and HELB outside containment. For each system within (including cables, EPAs, terminal blocks, etc.) the master list identify each Class IE electrical equipment item that is required to function under accident conditions. Pages 1 and 2 of Attachment 2 are standard formats to be used for the "master list" with typical information included.

Electrical equipment items, which are components of systems listed in Appendix A of Attachment 4, which are assumed to operate in the FSAR safety analysis and are relied on to mitigate design basis events are considered in the scope of this Bulletin, regardless whether or not they are classified as part of the engineered safety features when the plant was originally licensed

,to operate. The necessity for further upgrading of non-safety related plant systems will be dependent on the outcome of the licensees and the NRC reviews subsequent to TMI/2.

~Res onse The following additions to our March 28, 1980 submittal have been identified:

A) The 115/4.16KV reserve transformer and Reactor Protection System (RPS) Buses Il and 12 should be added t'o the list of electrical equipment common -to all systems. Attached is a revised table (Table 1) of electrical equipment common to all systems which includes these items.

B) Additional instrumentation systems'lectrical components, in areas exposed to harsh environmental conditions, are listed in Table 2. It should be noted that many components common to the Reactor Protection System are contained in the component list for reactor vessel instrumentation transmitted by Niagara Mohawk's March 5, 1980 response.

question 2 For each Class IE electrical equipment item identified in Item 1, provide written evidence of its environmental qualification to support the capability of the item to function under postulated accident conditions. For those Class IE electrical equipment items not having adequate qualification data available, identify your plans for determining qualifications of these items and your schedule for completing this action. Provide this in the format of .

~Res onse Our March 5, 1980 response provided system component evaluation work sheets for components inside the primary containment required to mitigate a loss of coolant accident (LOCA). The worksheets for electrical penetration assemblies and General Electric Vulkene cable should indicate that no thermal aging had been simulated. Attached are revised worksheets for these two components.

In our March 28, 1 response .to this question, it s stated that ev'aluation worksheets for components outside the primary containment would not be submitted unless it'was determined that such components are subject to harsh environments during a LOCA or high energy line break (HELB).

An evaluation of possible harsh environments outside the primary containment has been completed. This evaluation indicates that certain general areas may be subject to harsh environmental conditions of temperature and relative humidity. The specific results of this evaluation are included in response to guestion 3.

Niagara Mohawk is presently identifying equipment in the harsh environment areas outside the primary containment and will submit component qualification evaluation worksheets for such equipment by March 31, 1981.

(}uestion 3 For equipment identified in Items 1 and 2, provide service condition profiles (i.e., temperature, pressure, etc. as a function of time). This data should be provided for design basis accident conditions and qualification tests performed. This data may. be provided in profile or tabular form.

Response

Service conditions due to a LOCA inside the Nine Mile Point Unit 1 primary containment, were provided in the March 5, 1980 Niagara Mohawk submittal.

Evaluation of harsh environmental conditions due to HELB outside of the primary containment indicates that generally the react'or building and turbine building may see temperatures of 150F for extended periods of time, building design pressure ( less than 1 psig) and relative humidity of 100K on all elevations. Local areas may see direct'team or water impingement and higher temperatures.

Oetailed radiation service conditions outside of the Nine Mile Point Unit 1 primary containment following a LOCA are being evaluated. Preliminarily, it has been determined that the containment spray piping outside of the primary containment is the main shine source. Integrated radiation doses in areas where radiation sensitive- equipment may be located will be included in evaluation worksheets to be provided by March 31, 1981.

guestion 4 Evaluate the qualification of your Class IE electr ical equipment against the guidelines provided in Attachment 4. Attachment 5, "Interim Staff Position on Environmental gualification of Safety-Related Electrical Equipment", provides supplemental information to be used with these guidelines. For the equipment identified as having "Outstanding Items" by , provide a detailed "Equipment gualification Plan." Include in this plan specific actions which wi 11 be taken to determine equipment qualification and a schedule for completing the actions.

Response

The March 5, 1980 Niagara Mohawk response to I.E. Bulletin 79-01B contained qualification evaluation worksheets for electrical components within the primary containment required to mitigate a LOCA. Outstanding items on these worksheets are being further investigated as described below.

A) D. G. O'rien electrical penetration assemblies and General Electric Vulkene cable: Niagara Mohawk will test these components under LOCA service conditions including water spray and simulated thermal aging. Testing, to be performed by the Franklin Institute Research Laboratory will begin by November, 1980 and is expected to be completed by February, 1981.

B) Plans to address outstanding items for qualification of Limitorque valve operators, automatic depressurization system solenoids, and General Electric EB-5 terminal boards are to be reported by March 31, 1981. Gener'al Electric has been retained to evaluate this equipment and -this date is the earliest we expect results to be available.

The March 28, 1980 Niagara Mohawk response to I.E. Bulletin 79-01B contained qualification evaluation worksheets for electrical components inside the primary containment which are not required for LOCA mitigation but may be useful to the operator (referenced in LOCA procedure). Recirculation pump isolation valve motor operators are being addressed as indicated in Item 8 above for Limitorque valve operators., Instrumentation components within the primary containment will not be evaluated further. Caution will be provided in operator procedures r egarding the questionable qualification of operator aid type equi'pment by December 31, 1980.

Plans to address potential electrical equipment qualification deficiencies for equipment outside the primary containment will be reported by March 31, 1981. General Electric has been retained to perform the evaluation of this equipment and we have been informed that this is the best schedule we can expect due to similar work they are performing for other licensees.

(}uestion 5 Identify the maximum expected flood level inside the pr imary containment resulting from postulated'ccidents. Specify this flood level by elevation such as 620 ft. elevation. Provide this information in the format of .

~Res ense Maximum expected flood level elevation inside the pr imary containment resulting from postulated accidents has been previously identified in the March 5 and March 28, 1980 Niagara Mohawk submittals. It has been determined that the maximum expected flood level will be within the suppression chamber.

TABLE 1 SYSTEM ELECTRICAL EQUIPME COMMON TO ALL SYSTEMS COMPONENTS Location Plant Identification Inside Primary Outside Primary Number* Generic Name Containment Containment FLEXIBLE WATERTITE SEALTITE CONDUIT ELECTRICAL COND. VARIOUS SIZES SEALTITE FITTINGS FLEX. COND. FITTINGS VARIOUS SIZES J.B. IXXXXX-A JUNCTION BOXES THRU ZZZ VARIOUS SIZES COPE - TRAYMASTER CABLE TRAYS CABLE TRAY VARIOUS SIZES COPE - CAGE TRAY CABLE TRAY FITTINGS FITTINGS VARIUS SIZES 115/4. 16 KV RESERVE PREFERRED POWER FOR TRANSFORMER AUX. ELEC. EQUIP.

RPS BUS 11 5 12 120 V AC POWER

TABLE 2 SySTEM ADDITIONAL INSTRUMENTON COMPONENTS Location P1ant Identification Inside Primary Outside Primary Number* Generic Name Containment Containment 36-03A LEVEL TRANS.36-038 LEVEL TRANS.36-03C LEVEL TRANS.36-03D LEVEL TRANS.36-04A LEVEL TRANS.36-048 LEVEL TRANS.36-04C LEVEL TRANS.36-04D LEVEL TRANS.36-05A LEVEL TRANS.36-058 LEVEL TRANS.36-05C LEVEL TRANS.36-05D LEVEL TRANS.36-06A h PRESS. TRANS.36-068 4 PRESS. TRANS.36-06C ~ PRESS. TRANS.36-06D ~ PRESS. TRNAS.36-07A PRESS. TRANS.36-078 PRESS. TRANS.36-07C PRESS. TRANS.36-07D PRESS. TRANS.36-08A PRESS. TRANS.36-088 PRESS. TRANS.36-08C PRESS. TRANS.

36-OSD PRESS. TRANS.

TABLE 2 SySTEM ADO ITIONAL -INSTRUME TI ON COMPONENTS Location Plant Identification Inside Primary Outside Primary Number* Generic Name Containment Containment NR 108 A PRESS. SWITCH NR 108 B PRESS. SWITCH NR 108 E PRESS. SWITCH NR 108 C PRESS. 'SWITCH NR 108 0 PRESS. SWITCH NR 108 F PRESS. SWITCH 01-26A PRESS. TRANS.01-26B L PRESS. TRANS.01-26C a PRESS. TRANS.01-260 6 PRESS. TRANS.01-26E 6 PRESS. TRANS.01-26F 6 PRESS. TRANS.01-26G 5 PRESS.. TRANS.

Ol-26H a PRESS. TRANS.

201.2-476A PRESS TRANS.

201.2-476B PRESS. TRANS.

201. 2-476C PRESS. TRANS.

201.2-476D PRESS. TRANS.

1810A TEMP. SWITCH 1B10B TEMP. SWITCH 1810C TEMP. SWITCH 1B10D TEMP. SWITCH 1810E TEMP. SWITCH 1B10F TEMP. SWITCH

TABLE 2 1

.SYSTEM ADDITIONAL INSTRUMEIel'ION COMPONENTS Location Plant Identification Inside Primary Outside Primary Number* Generic Name Containment Containment 1810G TEMP. SWITCH 1810H TEMP. SWITCH 1810 J TEMP. SWITCH 1810K TEMP. SWITCH 1810L TEMP. SWITCH 1810M TEMP. SWITCH 1810N TEMP. SWITCH 1810P TEMP. SWITCH 1810Q TEMP. SWITCH 1810R TEMP. SWITCH RN05A RADIATION ELEMENT RN058 RADIATION ELEMENT RN05C RADIATION ELEMENT RN05D RADIATION ELEMENT RV45A ~ PRESS. SWITCH RV458 ~ PRESS. SWITCH RV45C ~ PRESS. SWITCH RV45D b, PRESS. SWITCH RN07A RADIATION ELEMENT RN078 RADIATION ELEMENT RN 04 RADIATION ELEMENT RN 04 RADIATION ELEMENT RN 04 RADIATION ELEMENT

TABLE 2

.SYSTEM ADDITIONAL INSTRUME ION COMPONENTS Location Plant Identification Inside Primary Outside Primary Number* Generic Name Containment Containment RN 04 RADIATION ELEMENT 1B06-13 TEMP. ELEMENT 1806-14 TEMP. ELEMENT TEMP. ELEMENT 1B06-23'806-24 TEMP. ELEMENT 201.2-476A-D (4) TRIP UNIT (MASTER) 36-03A-D (4) TRIP UNIT (MASTER) 36-03A-D (4) TRIP UNIT (SLAVE) 36-04A-D (4) TRIP UNIT (MASTER) 36-08A-D (4) TRIP UNIT (MASTER) 36-08A-D (4) TRIP UNIT (SLAVE) 36-05A-D (4) TRIP UNIT (MASTER) 36-06A-D (4) TRIP UNIT (MASTER) 01-26A-D (4) TRIP UNIT (MASTER) 01-26A-H (8) TRIP UNIT (MASTER) 36-07A-D (4) TRIP UNIT (MASTER) 36-07A-D (4) TRIP UNIT (SLAVE) 01-01 MSIV POSITION SWITCH 01-02 MSIV POSITION SWITCH 01-03 MSIV POSITION SWITCH 01-04 MSI V POSITION SWITCH I J12 FLOW TRANS.

IJ90 FLOW SWITCH

4 Facility:

Docket:

Nine Mile Point 50-220 Unit l SySTEM COMPONENT EVALUATION WORK SHEET ENVIRONMENT DOCUMENTATION REF.*

Equipment Description Qualification Outstanding Parameter pecification ualification Specification Qualification Method Items system: Containment Operating 60 Secs.*". 28 hrs 2.3 Simultaneous Plant ID No .Isolation H/A Time 5 None Temperature Component: El eCtri Cal SEE ACCIDENT Penetration Assemblies ~

( F) 2.3 Simultaneous Hone AND TEST Manufacturer: Pressure PROFILES PROVIDED D. G. O'rien (psia) 2.3 Simultaneous None 19 pin 816 Model No.: 5 pin 816 Relative 4 pin 88 Humidity looa 28 pin 816 l00% '4 23 Simultaneous Hone Function: El ectr i cal Penetrations Accuracy: Spec: H/A Spray NA HA Note I Demon: N/A Service: Containment Radiation I sol ati on 1.15 M rads 26 M rads Simulation None Location: Containment El'59', 237'ging NA NA NA'-" " Note -

Containment Flood Level: within torus Yes Submergence H/A H/A H/A N/A N/A Above Flood Level: No

<<Documentation

References:

notes:

1. FSM, Appendix E, Figures E-31 and E-33

2. FIRL Test Report F-C4879, dated December 1977

3. FIRL Report F-C4879-1, dated April 1978

4. Letter dated March 7, 1979, D.P. Disc (HMPC) to T. Ippolito (NRC)

5. FSM Ch.VI, Table VI-3

1. Evaluation to be performed to determine if qualification testing is. required

• • For accident profile below

Facility: Nine Mile Point Unit 1 SYSTEM COMPONENT EVALUATION 1 ei Docket: 50"220 f WORK SHEET

~ I 1

ENVIRONMENT DOCUMENTATION REF.*

Qualification Outstanding Equipment Description I

'Parameter pecification ualification Specification Qualification Method ,Items System: COntainmqnt Operating I Simultaneous Hone Isolatson j ~

'60 Secs ** 28 hrs 3 ~

Note 1 Plant ID No.: N/A Time Temperature 2.3 Simultaneous component: SEE ACCIDENT None .

Electrical'able

( F) Note 1 AND TEST Pressure PROFILES PROVIDED

'anufacturer:-

Simultaneous Hone General Electric (psia) 2.3 Note 1 Ho No.: Relative Simul taneous Hone Humidity 100% 100% 2.3 Note. 1 Function: POWer g, COntrO Note 2 Accuracy: Spec: H/A Spray NA NA Demon: H/A Simulation None Service: COntainment Radiation 1.15 rads 26 H rads N

Isolation Loca tion: COn ta nmeni t Aging NA NA'HA, Note 2 Containment Flood e Level: within torus yes Submergence N/A H/A H/A H/A N/A Above Flood Level: No

• Documentation

References:

Notes:

l. FSAR, Appendix E, Figures E-31 and E-33 l. qualified as part of the Electrical 2 FIRL Test Report F-C4879, dated December 1977

~ Penetration Assembly Tests

3. FIRL Test Report F-C4879-1, dated April 1978 2. Evaluation of ser vice conditions

".. Letter dated triarch 7, 1979, D.P. Disc (NHPC) to a9in9 and spray is being performed.

T. Ippoli to (HRC)

5. FSAR Ch. VI, Table VI-3

• • For accident profile below

0