ML20062E100

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Rept of SEP Reviewers Visit to Subj Facil on 780913-14 for Familiarization.Consisted Hydrological Review of Site & Region Outside the Site & Control Room Safety Sys Outside Containment.W/List of Participants
ML20062E100
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 11/21/1978
From: Fontecilla H
Office of Nuclear Reactor Regulation
To: Desiree Davis, Eisenhut D
Office of Nuclear Reactor Regulation
References
TASK-02-03.A, TASK-2-3.A, TASK-RR NUDOCS 7812040198
Download: ML20062E100 (6)


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November 21, 1978

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Docket No. 50-213

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MEMORANDUM FOR:

D. G. Eisenhut, Acting Assistant Director for Systems

& Projects, D0R THRU:

D. K. Davis, Chief, Systematic Evaluation Program Branch, D0R FROM:

H. M. Fontecilla, Systematic Evaluation Program Branch, D0R

SUBJECT:

VISIT TO HADDAM NECK PLANT A team of SEP reviewers visited the Haddam Neck plant on September 13 and 14, 1978, to familiarize themselves with the facility and to obtain additional i nfonna tion.

Lists of participants at these meetings are attached.

As part of the hydrological review of the site, we examined the following areas:

1.

Pump House 2.

Service water and circulating water system pumps 3.

Dewatering system sump and discharge canal 4.

Cooling water discharge canal 5.

Ditches east of plant s

6.

Drainage pond north of plant In addition, we examined the region outside the site, upstream and down-stream the Connecticut River, including the highway bridge several miles downstream from the plant.

During our meetings with the utility representatives we gathered the following infonnation:

2 1.

The roofs of safety-related buildings are designed for 30 #/ft snow and ice loadings.

781204ot93 V

D. G. Eisenhut November 21, 1978 2.

Based on pumping tests performed at a well field near the plant, the average permeabili ty of the outwash deposits on the banks of the Connecticut River is about 3000-5000 gallons per day per square foot.

It was felt that this would be a reasonable estimate of permeability of outwash deposits in the site area.

3.

Safety-related equipmelt will withstand a flood having an elevation of 23.5 f t ms), wi th no uther protection added.

The floor level is 21.5' and safety-related pumps are located about two feet above this elevation.

4.

A diesel fire pump is located in the pump house, which can be put into use if the other pumps fail.

This pump is at the same elevation as the other pumps (23.5' ).

5.

Some safety-related equipment is protected by 24" high steel dikes (walls) which surround the equipment.

When water (due to flooding) gets 1-2 inches high on these dikes, there are alarms which are activated, according to technical specifications.

6.

A dewatering system is used to lower grouna water levels around the reactor building.

At the present time, the design bases for the system or the design basis groundwater levels for the structures are not known.

Groundwater drained by the system flows to a pump, from which the water is pumped to a discharge ditch, which ultimately carries the flow to the cooling water discharge canal.

In the area of control room habitability, we obtained the following i nfo rma tion:

1.

No toxic chemicals are stored onsite.

s 2.

The control room walls and roof have a minimum of 18 inches of con-crete. The floor has 14 inches.

3.

The control room building is served by one HVAC system, not seismic Category I.

The nonnal air intake rate is 1500 cfm and the recircu-lation rate is 8000 cfm.

4.

There are no radition monitors in the fresh air intakes or in the control roan.

D. G. Eisenhut November 21, 1978 5.

Control room isolation is initiated by sensing a 4 psi overpressure inside the containnent building.

6.

The closing time for the fresh air intake isolation damper is 6.3 seconds.

7.

There is only one isolation damper.

It is designed to fail in a closed position.

8.

Leakage across the damper has been measured to be 500 cfm at a pres-sure di fferential of 1/8" water gauge.

9.

There is no air recirculation mechanism following isolation.

10.

Three airpaks of 120 f t each and eight air cylinders of 300 f t each are provided in the control room.

11. The control roan volume is 76000 f t.
12. The closest distance between the containnent building and the control room air intake is about 100 feet.

With regard to the review in the areas of tornado and turbine missile protection, we examined the location of most safety systems outside containment, and gathered the following information:

Auxiliary Building The Auxiliary Building consists of two levels. The first level floor elevation varies fran 13'6" to 21'6" and the floor of the second level varies from 35'6" to 36'6".

The grade level around the Auxiliary Buil di ng i s 21 ' 6".

The exterior walls extending up from the first level floor to the second level floor are steel reinforced concrete varying in thickness from 12" to 18".

The exterior walls extending up from the second floor level to the roof consists of insulated Galbestos on struc-i tural steel framing and the roof consists of metal panels covered with insulation and builtup roofing over a steel superstructure.

D. G. Eisenhut November 21, 1978 Turbine Building The Turbine Building consists of four levels.

The ground level is at elevation 21'6", first floor level is at elevation 37'6", second floor level is at elevation 47'6" and the operating floor is at elevation 59'6".

The exterior walls from ground level to roof consists of por-celain enamel siding supported on structural steel.

The roof consists of metal panels covered with insulation and builtup roofing over a steel supe rs truc ture. The floors consist of steel reinforced concrete.

Spent Fuel Building The Spent Fuel Building exterior walls consist of steel reinforced con-crete from elevation 21'6" up to elevation 47', except around the spent fuel pool which has walls 6' thick.

The exterior walls from elevation 47' to the roof consists of insulated Galbestos panels over a steel supe rs tructure. The roof consists of steel reinforced concrete 8" thick wi th a hatch extending partially over the spent fuel area. The hatch i s covered by 1/4" steel pla te. The operating floor of the Spent Fuel Building consists of steel reinforced concrete 12" thick.

On the east side of the building there is a 14' x 14' and a 10' x 23' galvanized steel rollup doors.

Screenwell House The Screenwell House exterior walls consist of insulated Galbestos panels over a steel superstructure. The roof consists of steel reinforced con-crete 8" thick with four large hatch openings of dimensions 17' x 10' covered wi th 1/4" steel plate.

In addition, there are about 6 additional smaller hatches and two large vents afforded similar 1/4" plate covers.

The traveling screens are outside of the Screenwell House facing the Connecticut Rig ?r and are covered by enclosures constructed of 1/8" steel plate.

Diesel Generator Building The Diesel Generator Building consists of 2' thick steel reinforced walls a nd roof s.

Each of the diesel generators and associated switchgear are separated by a l' thick steel reinforced concrete wall.

The 5000 gallon fuel tanks are buried such that the high point of each tank is below more than 7' of di rt.

D. G. Ei senhut

-5 tiovember 21, 1978 Containment The containment walls from elevation 6" to elevation 121' consists of steel reinforced concrete 4'6" thick.

The roof dome of the containment from elevation 121' to the top consists of steel reinforced concrete 2'6" thick.

Tne operating floor located at elevation 48'6" consists of steel reinforced concrete 2' thick. External to the containment but adjacent to the containment wall facing the Turbine Building and surrounding the main stemnline penetrations.

The wall from elevation 21' to 39'6" consists of steel reinforced concrete 6' thick.

The re-maining two levels consist of a steel superstructure with a facade of sidi ng. Tne floor at elevations 40'8", 49'8" and 57' consists of steel grating over I-beams. The main steamline isolation valves and relief valves are located at elevation 49'8".

The roof of the structure is at elevation 65'6" and consists of I-beams wi th a facade of metal siding.

Service Building The west wall of the Service Building is partially adjacent to the Auxiliary Building wi th the remainder of the wall shadowed by the contai nment. The south and east walls are adjacent to the Turbine Building and the north wall is adjacent to the new Diesel Generator Building up to about elevation 40'4".

That portion of the Service Building containing the control room consists of steel reinforced concrete. The remainder of the building consists of walls consisting of a steel superstructure with a facade of insulated Galbestos siding and a roof consisting of metal panels covered with insulation and a builtup roof over a steel superstructure. The control room (which is on the top floor of the Service Building at elevation 59'6") consists l

of exterior walls composed of 20" thick steel reinforced concrete of 3000 psi, interior walls composed of 16" steel reinforced concrete of 3000 psi, roof composed of 22" steel reinforced concrete of 3000 psi and floor composed of 14" steel reinforced concrete of 3000 psi.

In addi tion, the licensee agreed to prov1de us wi th information regarding the concrete walls (thickness, strength and height) surrounding the safety-related tanks (e.g., refueling water storage, etc.) onsite.

%%Ks&t Herbert M. Fontecilla Systematic Evaluation Program Branch Division of Operating Reactors

Enclosure:

As stated

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ENCLOSURE HADDAM NECK SITE VISIT PAR ICIPANTS i

September 13, 1978 NRC Connecticut Yankee H. Fontecilla, SEPB N. Burnett T. Johnson, HMB M. Morris W. Lazaros, I&E*

J. Ferguson*

R. Knoll, I&E*

NUSCO W. Rotherford L. Levy B. Ilberman i

September 14, 1978 NRC Connecticut Yankee H. Fontecilla, SEPB N. Burnett J. Wi ng, AAB M. Morris L. Bell, AAB NUSCO s

i R. Rodgers i

D. Miller P. Austin W. Rotherford i

R. McMillen i

L. Levy B. Ilberman Part time l

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