ML19326B811

Proposed Tech Specs 3.13 Re Hydraulic Shock Suppressors

ML19326B811
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/01/1975
From:	ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19326B807	List: ML19326B806 ML19326B811
References
NUDOCS 8004180561
Download: ML19326B811 (4)

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3 3.13 Hydraulic Shock Suppressors -

Applicability Applies to all hydraulic shock suppressors listed in Table 3.13-1.

Objective To casure adequate shock suppression protection for primary coolant system piping and any other safety related system or component under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. This is done by assuring the operability of those hydraulic shock suppressors installed for that purpose.

Specification 3.13.1 The reactor shall not be heated above 200oF if a hydraulic shock suppressor listed in Table 3.13-1 is known to be inoperable.

3. t.2 If a hydraulic shock suppressor listed in Table 3.13-1 is determined to be inoperable during power operation, that hydraulic shock suppressor shall be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the reactor shall be placed in the cold shutdown condition within an additional 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Bases Shock suppressors are designed to prevent unrestrained pipe motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motien during startup and ' shutdown. The-consequence of an inoperable shock suppressor is an increase in the pru-bability of structural damage to piping as a result of a seismic or other event initiating dynamic loads. It is therefore required that all hydrau-lic shock suppressors required to protect the primary cool. ant system or any other safety system or component be operable during reactor operation.

Because the shock suppressor protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed of r repairs or replacements. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a cold shutdown condition will permit an orderly shutdown consis-tent with standard operating procedures. Since plant startup should not commence with knowingly defective safety related equipment, Specification 3.13.1 prohibits startup with inoperable shock suppressors.

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' _) TABLE 3.13-1 r

SNUBBER 110. LOCATION, ELEVATI0ii 115 - 1 0 Pressurizer Relief Line A 409' - 2 3/4" liS-11 Pressurizer Relief Line A 16-12 410'~- 2/3/4" Pressurizer Relief Line A 410' - 2 3/4" 115 - 1 3 Pressurizer Relief Line A 400' - 0" llS-14 Pressurizer Relief Line A 400" - 0" HS-66 Pressurizer Relief Line C HS-67 410' - 2 3/4" Pressurizer Relief Line C 410' - 2 3/4" 11S - 6 8 Pressurizer Relief Line C 410' - 2 3/4" HS-69' Pressurizer Relief Line B HS-70 410' - 2 3/4" HS-71 Pressurizer Relie.f Line B 391' - 0" Pressurizer Relief Line A 367' - 6" HS-72 Pressurizer Relief Line A 3S7' - 0" H-A-1 Pressurizer Relief Line A 400' - 0" H-A-2 Pressurizer Relief Line A 399' - 0" 11-B-1 Pressurizer Relief Line B 400' - 0" li-B-2 Pressurizer Relief Line B 391' - 0" li-C-1 Pressurizer Relief Line C Il-C-2 410' - 2 3/4" Pressurizer Relief Line C 394' - 0" HS-3 ffain Steam Line A 425' - 0" llS-4 Main Steam Line A 408' - 6" liS-5 Main Steam Line A 428' - 0" IIS-6 Main Steam Line B 346' - 0" -

IIS-7 Main Steam Line B 420' - 0" 11S - 1 5 Main Steam Line A 408' - 6" HS-16 Main Steam Line B 423' - 2" HS-17 Main Steam Line B 423' - 2"

> HS-18 Main Steam Line B 408' - 6" 11S - 1 9 Main Steam Line B 396' - 0" HS-20 Main Steam Line B 408' - 6" HS-22 Main Feedwater Header B 11S - 2 3 376' - 4 11/16" Main Feedwater Header B 376' - 4 11/16" HS-24 Main Feedwater Header B HS-25 376' - 4 11/16" Main Feedwater Header B 376' - 4 11/16" IIS-26 Main Feedwater Header B 15-27 376' - 4 11/16" e

Main Feedwater Header B 376' - 4 11/16" HS-28 Main Feedwater Header B IIS-29 376' - 4 11/16"

!!ain Feedwater Header B 376' - 4 l'1/16 "

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' Main Feedwater Line A 361' - 0" HS-31 Main Feedwater Header A

~ IIS-32 376' - 4 11/16" Main Feedwater lleader A 376' - 4 11/16" IIS-33 Main Feedwater lieader A IIS-34 376' - 4 11/16" Main Feedwater lleader A 376' - 4 11/16" IIS-35 Main Feedwater llcader A llS-36 376' - 4 11/16,"

Main Feedwater IIcader A 376' - 4 11/16" 11S - 3 7 Main.Feedwater lleader A 376' - 4 11/16" 11S - 3 8 Main Fe. water lleader A 376' - 4 11/16" ilS-21 Emergency Feedwater Line B 394' - 0"

' 1A Reactor Coolant Pump A 2A 390' - 10" Reactor Coolant Pump A 390' - 10" 1B Reactor Coolant Pump B 390' - 10" 2B Reactor Coolant Pump B 390' 10" 1C Reactor Coolant Pump C 390' - 10" 2C Reactor. Coolant Pump C 390' - 10" 1D Reactor Coolant Pump D 390' - 10" 2D Reactor Coolant Pump D 390' - 10"

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4.16 SPECIAL SURVEILLANCE i

Applicability Applies to miscellaneous surveillance items not covered by other specifi-cations .

Objective To provide special surveillance for items not covered by other specifications.

Specification 4.16.1 The following surveillance requirements apply to all hydraulic

. ;ck suppressors listed in Table 3.13-1.

4.16, ydraulic shock suppressors shall be visually inspected to

, .ay their operability in accordance with the following mini-mum frequency schedule:

Number of Shock Suppressors Next Required Found Inoperable Inspection During Inspection Interval or During Inspection Interval 0 Each Refueling Period 1

12 months 2 6 months 3,4 124 days 5,6,7 62 days

>8 31 days The required inspection interval shall not be lengthened more i than one step at a time.

Shock suppressors may be categorized in two groups, " accessible" or " inaccessible" based on their accessibility for inspection during reactor operation. These two groups may be inspected inuependently according to the above schedule.

4.16.1.2 Once cach refueling period at least two representative snubbers from a relatively severe environment shall be completely elis-assembled and examined for damage and abnormal seal degradation.

4.16.1.3 The first inspection required by 4.16.1.1 shall be done during the'first refueling shutdown following issuance of this speci-fication. The schedule of 4.16.1.1 shall be entered at the "Each Refueling Period" interval point.

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Bases All safety related hydraulic shock suppressors are visually inspected-for "overall integrity and operability. The inspection will include verifica-tion of proper orientation, adequate hydraulic fluid level and proper attachment of suppressor to piping and structures.

The inspection frequency is based upon maintaining a constant level of shock suppressor protection. Thus the required inspection interval varies inversely with the observed shock suppressor failures. The number of inoperable shock suppressors found during a required inspection determines the time interval for the next required inspection. Inspections performed before that interval h.s elapsed (nominal time less 25%) may be used as a new reference point to determine the next inspection. However, the results of sudi carly inspections may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule. Since no hydraulic shcek suppressor have

' previously been found to be inoperable the schedule of 4.lu.1.1 will be entered at the 18 month interval point.

If the categorization option of 4.15.1.1 is used all hydraulic shock suppressors in the reactor building shall be considered inaccessible and all others shall be categorized based on radiation levels, ambient conditions and other occupational hazards.

To complement the visual external inspections, disassembly and internal examination for component damage and abnormal seal degradation should be performed. The examination of two units, each refueling cycle, i

selected from relatively severe environments should adequately serve this purpose. Any observed wear, breakdova or deterioration will provide a basis for additional inspections.

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