ML20246D938

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Forwards Corrected Sections 2.3.1 & 2.3.4 to Annual Update to Solid Waste Staging Facility Sys Description
ML20246D938
Person / Time
Site: Crane Constellation icon.png
Issue date: 08/21/1989
From: Roche M
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
4410-89-L-0094, 4410-89-L-94, NUDOCS 8908280337
Download: ML20246D938 (3)


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s GPU Nuclear Corporation Nuclear

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Middletown. Pennsylvania 17057-0191 717 944 7621 TELEX 84-2386 W-riters Direct Dial Number:

(717) 948-8400 August 21, 1989 4410-89-L-0094/0051P US Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk-Three Mile Island Nuclear Station, Unit 2 (TMI-2)

Operating License No. DPR-73 Docket No. 50-320 Solid Waste Staging Facility System Description

Dear Sirs:

GPU Nuclear letter 4410-89-L-0084, dated August 8, 1989, submitted the annual update to the Solid Waste Staging Facility System Description. Attached is a correction to a typographical error in Sections 2.3.1 and 2.3.4 (i.e., changed Regulatory Guide 1.43 to 1.143).

Sincerely,

  • f f 6p er G

f N. B. Roche Dire:: tor, TRI-2 RDW/ emf

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cc:

W. T. Russell - Regic,nal Administrator, Region 1

0. F. Stolz - Director, Plant Directorate IV L. P. Thonifs - Project Mainger, TMI Site F. I. Young - Senior Resider.t inspector, TMI 8908280337 890821 h

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GPU Nuclear Corporation is a subsidiary of the General Pubhc Utihties Corporation

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c 3184-007 2.1.3.4.

A floor drainage system is incorporated into the module design which discharges into a common sump located between Modules "A" and "B".

The total capacity.of the sump is approximately-2750 gallons.

2.2c. References 2.2.1 U.S. Nuclear Regulatory Guide 1;143, July.1978, Design Guidance, for Radioactive Management Systems, Structures, and~ Components

~ Installed'in Light-Water-Cooled Nuclear Power Plants'.

2.2.2 Design Criteria / Input Record. GAI H.O. 104-4283-070.

2.2.3 Gilbert Associates. Inc. (GAI) Drawings:

2.2.3.1 Excavation and Grading Plan. E-774-151, 2.2.3.2 Plant Layout.

E-012-006 E-014-004.

2.2.3.3 Structural.

E-430-006 E-430-007 E-430-008 E-430-011 E-430-012 E-430-013 E-430-014 E-430-015.

2.2.3.4 Building Services-Piping.

E-'311-873 E-311-874.

i 2.2.3.5 Electrical.

SS-308-417 i

B-256-031 E-266-011.

2,.3. Design Sasis

2. 3.1 The SHSF is designed to comply with the requirements of Regulatory t

Guide 1.lf43 July 1978 The facliity is des *9 red to provide &

contro11ti but reacy aces; for ntates tal hardling aptrations and to s.nsure that t.he oper,stor exposures are is low as is reasonably achievable (ALARA?.

2.3.2 The facility is designed to maintain the dose rates in accordance with 10 CFR Part 20 and to meet the requirements of 40 CFR Par' 190 at the site boundary and beyor.d.

l 2.3.3 The shielding thictr.eas was calcJ1ated to limit the contact dose rates at the outer surfaces of tne module walls and the top of the cell covers to within 0.5 mr/hr and 2.5 mr/hr, respectively. The y

analysis was based on the types of waste defined in Attachment 1.

No credit was taken for the structure being partially underground. Rev. 4/0051P lL W___-__

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3104-007-

'2.3.4-Quality Assurance requirements for the design, construction, and operation of.the.SWSF are consistent with those specified in Regulatory Guide 1.143.

2.4: Summary System Description 2.4.1 The concrete ~ structure and. individual' cell covers provide ths necessary shielding from the radioactive waste housed in the SWSF

. Module Storage Cells.

.The ceII. covers with gaskets protect the waste containers from the

-elements-and the ingress of precipitation.

Slots and weep-holes in the upper module structure are provided to direct rainwater to external. drainage ditches. A drainage piping system prevents any spillage / leakage of fluids from accumulating in the. cells (i.e.,

' floor drain hub in each cell); the system manifold discharges into a common sump, 2.4.2The sump compartment, a radwaste seismic concrete structure, houses'the pump, valves, piping, instrumentation,-etc.. necessary to perform the intended functions and control the disposal of any effluent which may collect in the sump. The compartment is divided into two (2) levels, with the upper operator level T

shielded by:a thick concrete floor from the sump. Access to the

' upper compartment is via'a manhole in the concrete slab roof.

Access to the sump is via a removable. ladder at the~ sump' plug opening'and a permanently installed ladder.into the sump.

2.4.3 Th'e flow diagram (Figure 3) shows the pumping system for the sump effluent. All operations are local / manual. The local alarms and sump level indication are housed in a weatherproof instrumentation

'oanel' mounted outside the Module "A" structure adjacent to the sump compartment.

The sump pump, Scienoid Valve #WS-5 and three-way valve #WS-1 (extension spindle) are located in the lower sump while the electrical distribution and control panels, valves, etc. are mounted in the operators compartment.

Sump itvel is meast ad by a variable capacitance sensor (SHS-LE-?l) which u nsmits the signal to local and remote (Unit 2 Control Room) alart.

Sump influent flow alarms are provided.

The sensing elements (conductivity) Nos. SWS-CE-07 and SWS-CE-08 are mounted in the Module "A" and "B" drain system manifold.

'2. 4.3.1 Sump Pumping Operations (See Figure 3)

The SWSF sump is controlled and disposal of the effluent is in accordance with the Unit 2 Procedures 4210-0PS-30ll.01 and 4215-0PS-3232.14.

The sump' compartment is posted as a radiological controlled area and surveillance is required prior to entry to ensure operator exposure will be as low as is reasonably achievable (ALARA). Rev. 4/0051P 2

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