ML20127F257

Notice of Violation from Insp on 850223-0324

ML20127F257
Person / Time
Site:	Hatch
Issue date:	04/22/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20127F234	List: IR 05000223/2003024 ML20127F229 ML20127F257
References
50-321-85-09, 50-321-85-9, 50-366-85-09, 50-366-85-9, NUDOCS 8505200375
Download: ML20127F257 (3)

See also: IR 05000223/2003024

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APR 221985

ENCL 0SURE 1

NOTICE OF VIOLATION

Georgia Power Company Docket Nos. 50-321 and 50-366

Hatch Units 1 and 2 License Nos. DPR-57 and NPF-5

The following violations were identified during an inspection conducted on

February 23 - March 24,1985. The Severity Levels were assigned in accordance

with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1. Technical Specification 6.8.1.c requires that written procedures be

established covering surveillance and test activities of safety-related

equipment.

Contrary to the above, written procedures were not established for Units 1

and 2 on February 28, 1985, to cover the following Technical Surveillance

Requirements on safety-related systems:

a. Unit 1 Technical Specifications 4.6.0 and 4.6.E require the permanent

recording of reactor coolant temperatures in the operating loop, idle

loop, steam dome and bottom head drain prior to startop, of an idle

recirculation loop. Retention of recorder tapes for these parameters

is 5 years vs. permanent and no other logging is specified '

by Hatch

procedures.

b. Unit 1 Technical Specifications 4.6. A and Unit 2 Technical Specifi-

cations 4.4.6.1.1 require that reactor coolant system temperature and

pressure be verified within limits at least every 30 minutes during

reactor coolant heatup and cooldown,

c. Unit 2 Technical Specifications 4.4.6.1.2 requires that reactor coolant

system temperature and pressure be verified within limits within 15

minutes prior to withdrawal of control rods to bring the reactor

critical.

This is a feverity Level IV violation (Supplement I).

2. Technical Specification 3.6.B requires that:

The reactor vessel shell temperatures during inservice hydrostatic or

leak testing shall be at or above the higher of the temperatures shown

on the curves of Figure 3.6-2 where the dashed line curve, RPV core

beltline region is increased by the expected shif t in RT NOT from

Figure 3.6-1.

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APR 231985

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Georgia Power Company Docket Nos. 50-321 and 50-366

Hatch Units 1 and 2 2 License Nos. DPR-57 and NPF-5

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During heatup by non nuclear means, cooldown following nuclear shutdown

or low level physics tests, the reactor vessel shell and fluid

temperatures of Specification 4.6. A shall be at or above the higher of

the temperatures shown on the curves of Figure 3.6-3 where the dashed

line curve, initial core beltline region is increased by the expected

shift in RT NOT from Figure 3.6-1.

During all operation with a critical core, other than for low level

physics tests, the reactor vessel shell and fluid temperatures of

Specification 4.6.A shall be at or above the higher of the temperatures r

shown on the curves of Figure 3.6-4 where the dashed line curve, [

fnitial core beltline region is increased by the expected shif t in

RT

NOT

from Figure 3.6-1.

Contrary to the above, the licensee did not have a procedure issued to

implement the requirements of Technical Specification 3.6.B nor did the

licensee perform the required corrections of the stated curves.

This is a Severity Level IV violation (Supplement I). Applicable to Unit 1

only.

3. Technical Specification 6.8.1 requires that procedures shall be established,

implemented and maintained covering safety-related activities.

Contrary to the above:

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a. Procedure HNP-1-3407, Suppression Chamber Delta Temperature (RCIC)

Instrumentation Functional Test and Calibration, was not properly

implemented in that on January 23, 1985 personnel placed clearance hold

tags on the Traveling Incore Probe (TIP) mode switches vs. the drive

switches as required by Procedure HNP-1-3407. This resulted in the TIP

ball valves being unable to automatically shut upon receipt of a

Group 2 Primary Containment Isolation System (PCIS) signal as required

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by Technical Specifications Table 3.7-1. ,

b. Procedure HNP-1-3417, RCIC Pump Suction Pressure Instrument Functional

Test and Calibration, and Technical Specification Table 4.2-3 Item 4, '

require monthly instrument functional test for RCIC pump suction

pressure instrument. Proceduro HNP-1-3417 was not properly implemented

in that the required surveillance test was not performed within the

specified frequency time limits due to personnel error,

c. Procedure HNP-2-3410, RCIC Steam Line Delta Pressure Instrument

Functional Test and Calibration, was not properly maintained in that a

revision was issued to the procedure which contained engineering errors

resulting in an improper and non-conservative set point for RCIC steam

line differential pressure. This is contrary to Technical Specifi-

cation Table 3.3.2-2. Item 5.

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This is a Severity Level IV violation (Supplement I).

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Georgia Power Company Docket Nos. 50-321 and 50-366

Hatch Units 1 and 2 3 License Nos. OPR-57 and NPF-5

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Pursuant to 10 CFR 2.201, you are required to submit to this office within 30  !

days of the date of this Notice, a written statement or explanation in reply,

including: (1) admission or denial of the alleged violations; (2) the reasons I

for the violations if admitted; (3) the corrective steps which have been taken

and the results achieved; (4) corrective steps which will be taken to avoid ,

further violations; and (5) the date when full compliance will be achieved. l

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Security or safeguards information should be submitted as an enclosure to  !

facilitate withholding it from public disclosure as required by 10 CFR 2.790(d)

or 10 CFR 73.21.

Date:

A R 221985

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