ML19340B385

Tech Spec 4.3 for Inservice Insp of Reactor Coolant Sys

ML19340B385
Person / Time
Site:	Oyster Creek
Issue date:	10/17/1980
From:	JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19340B384	List: ML19340B383 ML19340B385
References
TASK-05-04, TASK-5-4, TASK-RR NUDOCS 8010220389
Download: ML19340B385 (3)

Text

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4.3-2 l

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l condition of th'e coolant system and to ensure its continued

! integrity this surveillance program was developed. The program includes detailed controlled and documented inspections of all significant system components. A representative sample

• of selected components will be periodically inspected with l emphasis being placed on those areas subject to the highest service factors. The program parallels the requirements set forth in AShE Boiler and Pressure Vessel Code,Section XI 1971 .

Edition with its addenda through Summer 1973 to the maximum extent possible with due consideration given to physical access

! and radiation limiting conditions, hhen acceptance criteria are not delineated in this code, the 1974 Edition with addenda through Summer 1975 or the 1977 Edition with addenda through Summer 1978.will be followed.

The system pressure test will be conducted at a pressure greater than 800 psig. This pressure range has been selected

because of the difficulty experienced in the past with safety

! valves weeping while the plant is cold, and with the pressure l in the range of 900 to 1000 psig. The weeping allows foreign particles to become lodged between the disc and the seat and causes leakage during operation. Gagging the valves repeatedly substantially increases the possibility that they will be damaged and their set points altered and, therefore, has been ruled out.

The hydrostatic pressure test which shall be conducted at or near the end of each inspection interval will be conducted at a pressure which satisfies Part IS S00, ASFE Section XI.

l During the hydrostatic pressure test the safety valves will be gagged.

The test frequency for safety valves is in accordance with that recommended by Part IWV ASFE Section XI. The acceptable set point tolerance of + lt as specified in Part NB ASFE Section i III.

l Conductivity instruments continuously monitor the reactor coolant. Experience indicates that a check of the conductivity instrumentation at least every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is adequate to ensure

!~ accurate readings. The reactor water sample will also be used

! to determine the chloride ion content to assure that the limits l of 3.3.E are not exceeded.

801o2 6 3R9 .. .

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43.-9 NOTE 1 - The volume or surface area of metal to be. included in each inspection shall be in accordance with' that specified by ASME Section XI with Addenda through Summer of 1973 to the extent that accessability and component . configuration permits. '

NOTE 2. - For. the purposes of this inspection program, the four inspection intervals are defined as follows:

a) .1969-1979.

b) 1980-1989 c) 1990-1999 d) 2000-2009 -

However, each of the inspection intervals mentioned above can be adjusted by.as much as one year to; accommodate the plant outage schedule as allowed by the ASME Code.

NOTE 3 - The area inspected during an individual examination shall provide a representative sampling of the entire weld.

NOTE 4 - No more than one (1) examination is required of an individual component during an inspection interval.

NOTE 5 - Visual inspections may be performed by Engineers, or Quality Assurance, Mainteaance 6 Operations personnel technically qualified to make the inspection. '

NOTE 6 - 1. All welds shall be inspected in each third of the remaining (2/3) two-thirds of the first inspection interval (1969-1979).

2. If no defects are found, or the defects do not exceed the allowable standards, during the inspection of 1. , above, subsequent inspection may be limited to once during each inspection interval.

3. If defects are detected that exceed the allowable standards; an additional number of welds in this category, approximately equal to the number initially examined, shall be inspected. If further in-t dications in excess of allowable standards are revealed, all of the reraining welds in this category shall be inspected. Each weld in this category shall then be inspected once each 1/3 interval for three consecutive 1/3 intervals.

a The following notes' apply to 'the first inspection interval only and are a result of conversations between JCPGL

' . staff and NRC staff. They modify the requirements for the first inspection interval to reficct examinations in

. inspection prior to December 31, 1975.

NOTE 7f- One (1) examined in 1971, the remaining two (2) to be examined 1 7 the end of the first interval .

s NOTE 8 - All completed in 1971 - No additional examinations this interval.

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s 2.3- b) All other postulated pipe break b) A representative sample of The welds to be (C:nt.) welds. all physically accessible examined are de-

> welds listed under b) total- scribed in Rev.1 ing approximately 25% shall Supplement 6, be examined within each in- Addendum 6. Amend-

- spection interval. ment 68.

Note 11 2.4 Circumferential and longitudinal Visual Ouring The examinations shall cumula- Note 5

welds in piping of nominal pipe pressure tively cover 100% of all sub-size 1 inch and smaller.' tests) ject welds during the inspec-tion intervals..

2.5 Piping supports and hangers Visual The inspections performed Note 5

. excluding hydraulic seismic restraints. during each inspection in-terval shall cumulatively cover all support members and structures.

2.6 Hydraulic Seismic Restraints (See Sections 3.5.7 and 4.5.0)

Integrally welded linear type Visual & The examination shall be Note 4 2.7 l support attachments in tension Surface performed whenever the area is uncovered for other main-tenance activities.

3.0- Pumps 3.1 The internal pressure boundary' Visual The inspection shall be per- Note 5 surface of the recirculation formedwheneversubjectpump(s)

> pumps, are disassembled f>r maintenance. ,

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