ML19276H297

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Summary of 740115 TMI-1 Site Visit to Perform Overall Review of Emergency Feedwater Sys Controls & Installation,Reactor Bldg Surveillance,Installation of Kidney Filter,Leak Test Requirements & Addl Containment Isolation Valves
ML19276H297
Person / Time
Site: Crane Constellation icon.png
Issue date: 01/23/1974
From: Bernero R
US ATOMIC ENERGY COMMISSION (AEC)
To:
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7910160641
Download: ML19276H297 (9)
v • d • e


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50-239 4

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WO APPLICANT : METROPOLITX1 ZLI50:7 COMFK!i FACILIT'i

THREr HILE ISL.GD, GIT 1 RZF0ET OF SITE VISIT G5 JAMPLU 15, 1974 This site vicit was made to (1) perform an overall review of the installation and e strols of the energency feedvater systc;, (2) discuss requirert_n.s for reactor building surveillance during the forthconing structural integrity test, (3) to discuss implementation of 10 CFR 50 Appendix J for reactor building leak testing, and (4) to discuss the design and pr :irement status of the " kidney" filter required by the agreement with intervenors. A list of attendees is attached.

Summary An overall review of the emergency feeducer systen was r.ade by walkthrough and detailed discussion. The reactor building surveillance and Icak test requirements vere discussed, the need for an additional containment isolation valve was identified. The applicant presented a sumary of the design and installation steus of the new reactor building kidney filter.

A.

Energency Fcedvnter Systen (EW)

An overall review of the installation and controls of the emergency feedvater system was made. A set of notes describing the systen are attached to this report. The design basis and reliability of the system were discussed with the applicant after the walkthrough inspection. The applicant peinted out that the EW system was designed to satisfy 1968 General Leaign Criterion No. 6 which calls for a reliable system for decay heat removal. The design aspects covered in the attached notes were verified and various failure raodes were discussed. The applicant pointed out that the reactor coolant system fead-and-bleed technique described in Istendment 43 to the Fint Safety Analysic Report is a backup to the EW system. The applicant reiterated the intent to install a strainer in the line connecting the low pressure injection (LPI) system to the high pressure injection (EPI) systen; the strainer is on order with delivery expected in add 1974. It is not certain that the strainer o rrec s

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'ceting Su:=ary JAS 2 3 57.t is needed, but the concern arises from the fact that the LPI pucps are capabla of pacsing debris which cculd dar-m e the closer fit ITI pt=ps.

Thus if the feed-and-bleed technique van used, and its use continued into the recirculation rede (af ter c ptyine the borated water storage tank), the water in the reacter buil.iin; su=p would be picked up by the L?I pump, boosted to the suction of the IIPI pump, and then pt.mped back into the systen, The possibility of ingesting debris from the reactor building flocr is the reason for the strainer.

The applicant also clarified the technique used to codel the pressurizer relief valve for the feed-and-bleed analysis.

It was assumed that the valve begins to open at 2475 psig and is full open at 2500 psig.

B.

Ring Girder Surveillance The applicant was presented with copies of the recent staff letter calling for clarification of the surveillance to be conducted during the reactor building Structural Integrity Test (SIT). The applicant intends to conduct full rin8 S rder surveil unce during i

the SIT; the test is currently scheduled for February 18, 1974.

The applicant expects to respond to the staff letter by February 1, 1974; their responsa vill also include a comparison of their SIT procedure to Regulatory Guide 1.18.

C.

10 CFR 50, Apoendix J The applicant reviewed the plant design for compliance with Appendix J and identified 5 sets of valves where the requirement for Appendi: J Type C testing is questioned. The sets of valves and the AEC position given to the applicant are:

1.

P3-V2 and RB-V7 (inlet and outlet valves on Reactor Euilding nor=al ecolin;; coils): Type. C testing is required for these valves. Moreover, RS-V2 in a check valve and is not acceptable as the isolation valve for the inlet line. The applicant was informed that an autocatic isolation valve sini br to RS-V7 would have to be added. The applicant promised to give an initial schedule for this action within a week.

2.

RR-V3A. B, C and RR-V4A, D. C, D (inlet and outlet valves on Reactor Building emergency cooling coils): Type C testing is not required by Appendix J.

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NS-V52A, 3, C and :;S-V53A, 3, C (inlet and cutler valves en Reactor 14uilding main recirculating fan : rotor ecclers): Type C testing is not required by Appendin J.

4.

DH-V2 and tH-V3 (Reactor Coolant Systen to Decay IIeat Rerc. oval System pu=p suction line): Typu C testing is not required since these valves t:ust not be cpened while the plant is at pressure ner closed when it is depressurized.

5.

AII-V13 and AH-VIC (valves inside containnent on Reactor Building purga lines): In accordance with Appendix J, Type C testing by pressurizing between the valves is acceptable.

D.

Kidney P11ter The applicant agreed, at the public hearing for the operatinr.

License, to install a recirculating charcoal filter in the Reactor BuildinE to further reduce activity releases from building purge.

At this meeting th i applicant was asked to present the design and insea11ation status of this filter.

The filter is designed for 18,000 CFM flow and consists of a series array of roughing filter, HEPA filter, charcoal filter, and second EPA filter. The ductwork for this filter and its fan will tie into the purge inlet ducting for good air circulation in the building (the two systems do not operate at the same time).

A 1500 gallon water tank and puerp system will be provided to quench any fires caused by fission product heat.

Hardware procurecient is proceeding uith completion of deliveries expected by surner. Fabrication of the fire water tank is being accelerated in an attempt to deliver it to e Reactor Building before the main equipment hatch is closed. 1he applicant c=pects to submit a letter report on the final design of this filter by April of 1974.

E.

Other Items A set of AEC cor.= tents on the proposed Technical Specifications were recently given to the applicant. These were discussed briefly.

The applicant asked what itans must be resolved before Three Mile Island Unit 1 can be licensed. The following principal outstanding items were enumerated:

1.

Resolution of concents on Technical Specificat

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2.

Approval of the Operational Quality Assurance

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Form AEC-319 t Rev. 9-93) AICM 02 0 o*o c.3 is o s.e s-i s a o.a *.

Meeting Su rar/ JAN 2 3 ip4 3.

Satisf actory conduct of the 7ecctor 72uilding Struer. ural Integrity Icst, 4.

Closecut of the AEC ?.0--I Outctanding Itcs List.

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Robert M h,stnero, Project 'farager Light Water React.m Br. tio. 2-3 Directorate of Licensing

Enclosure:

Attend.,nce List DISTRIBUTION:

AEC PDR Local PDR Docket LWR 2-3 Rdg L Rdg RP Rdg RP AD's RP BC's S. Varga D. Eisenhut J. Hendrie TR AD's TR BC's F. St. Mary R. M. Bernero P. Seiffert R0 (3)

EIGoulbourne RS (3)

ACRS (16)

B. W. Washburn J. D. Orndoff R. L. Spessard, RO:I

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  • Form AEC-318 (Rev. 9-33) AEC.M 0240 GPO C43 IS S t edS 9 530 484

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.r J44 23 r>/4 ENCLOSURE I LIST OF ATTENDEES JANUARY 15, 1974 THREE MILE ISIAND UNIT 1 DOCKET No. 50-289 U.S. Atomic Energy Commission R. M. Bernero B. W. Washburn J. D. Orndoff R. L. Spessard General Public Utilities Service Corp.

R. W. Heward, Jr.

W. T. Gunn J. P. Moore D. H. Reppert J. M. Vann R. A. Burns J. J. Barton Babcock and Wilcox Company G. F. Glei W. S. Delicate Gilbert Associates, Inc.

W. F. Sailer J. E. Behan, Jr.

V. H. Willems D. D. Krause S. Hunt h?

m ENCLOSURE II JAN 2 3 1974 NOTES THREE MILE ISLAND 1 DOCKET No. 50-289 T.MEP.GENCY FEEDWATER SYSTEM (EFW) 1.

All pumps, piping, and valves are seismic I, including the condensate tanks.

2.

The turbine-driven pump (EF-P1) is started automatically upon loss of either reactor coolant pump power or loss of main feedwater system power. A separate control system starts the pump by opening de-powered valves MSV 13 A, B (high steam pressure) or MSV 10 A, B (low steam pressure). The Integrated Control System (ICS) regulates feedwater flow by controlling valves EFV 30 A and B.

3.

The two motor-driven pumps (EFP-2A and EFP-23) are started manually from the Control Room.

4.

The operator in the Control Room has seismic I steam generator level information, but no EFW flow indication.

5.

The following valves have remote controls and position indication in the Control Room: MS-V-10 A MS-V-10 B MS-V-13 A MS-V-13 B EF-V-1 A EF-V-1 B EF-V-2 A EF-V-2 B EF-V-30 A (auto. or manual)

EF-V-30 B (auto or manual) 6.

The valves named in note 5 have handwheels and are located in one area about 2 minuterwalk from the Control Room.

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JAN 2 3 r374 7.

The motor-driven pumps, EFP-2A and EFP-2B are normally powered from the red and green emergency diesel busses, respectively. However, each emergency bus has a breaker for each pump and the operator may place either or both on either bus. The power cables connecting the pumps to the busses each have a short section (- 50 ft.) which is not seismic I, although in a seismic I building.

8.

All valves designated with the suffix A in note 5 are powered from the red emergency power source (ac or de) and all valves designated with the suffix B are powered from the green source. The power and control cables for these valves are not certified as Class IE and cable separation is not assured.

9.

Air-operated regulating valves EF-V-30 A and 30 B each have an air accumulator to assure operability after a loss of air supply.

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