ML20031D825

Proposed Tech Spec Sections 3.6.I & 4.6.I Re Snubber Surveillance

ML20031D825
Person / Time
Site:	Millstone
Issue date:	09/30/1981
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20031D824	List: ML20031D823 ML20031D825
References
NUDOCS 8110140263
Download: ML20031D825 (11)

Text

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Docket No. 50-245 1

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Attachmer.t 4

Millstone Nuclear Power Station, Unit No. 1 4

Proposed Technical Specifications 1

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I 1e September, 1981 4

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LIMITING CONDITION FOR OPERATION SURVEILLANCE RE(UIREMENT l

3.6.1 SNUBBERS 4.6.1 SNUBBERS

1. The snubbers listed in Tables 3.6.1.a and Each snubber shall be demonstrated OPERABLE by prefom-3.6.1.b are required to protect the reactor cool-ance of the following augmented inservice inspection ant system or other safety related systems or program.

components.

2. During all modes of operation except cold shut-1.

Visual Inspection down and refueling, all snubbers shall be oper-All snubbers shall be visually dnspected in accord-able.

ance with the following schedule.

3. If a snubber is determined to be inoperable, con-

1. of Snubbers Found tinued reactor operation is permissible only during the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following such determination c

or ing Next Required unless the snubber is sooner replaced, made oper-Inspection Interval Inspection Interval able, or an engineering evaluation determined the supported system / component to be operable 0

18 months i 25%

1 12 months i 25%

with the inoperable snubber.

2 6 months i 25%

4,, If the requirements of 3.6.1.2 and 3.6.I.3 cannot 3,4 124 days i 25%

be met, an orderly shutdown shall be initiated and da i

within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

--k6,7 the reactor shall be in a cold shutdown condition The required inspection interval shall not be l

5. If a snubber is detemined to be inoperable while lengthened more than one step at a time.

the reactor is in the shutdown or refueling mode, the snubber shall be made operable or replaced Snubbers may be categorized in two groups, mechanical prior to reactor startup.

and hydraulic. Each group may be divided into two 4

subgroups; those accessible and those inaccessible

6. Stubbers may be added to or deleted from safety during reactor operation. Each group and subgroup related systems without prior License Amend Mnt may be inspected independently in accordance with to Tables 3.6.1.a and 3.6.1.b provided that the above schedule.

safety evaluations, documentation, and reporting

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are provided in accorde.nce with 10 CFR 50.59 and that a proposed revision to Tables 3.G.1.a and 3.6.1.b is included with the next License Amend-ment Request.

3/4 6-12 I

SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION 2.

Visual Inspection Acceptance Criteria l

Visual inspections shall be conducted in the following manner:

(a) in the case where the attachments to the foundation or supporting structure are found to be insecure, the cause of the rejection shall be clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; or (b) if there are visual indications of damage or impaired OPERABILITY, the affected snubber shall be tested in the as-found condition and, if determined OPERABLE per specifications 4.6.I.4a or 4.6.I.4b as applicable, may be excluded from the number of snubbers counted as having failed the visual inspection. Snubbers which appeared inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval provided that the above procedure is adhered to.

3.

Snubber Tests At least once per eighteen (18) months during shutdown, a representative sample (10% of the total of each type of snubbers, mechanical and hydraulic, in use in the plant) shall be tested either in place or in a bench test. For each snubber that does not meet the test acceptance criteria of Specification 4.6.I.4a or 4.6.I.4b as applicable, an additional ?0% of that type of snubber shall be tested. Tables 3.6.la and 3.6.lb may be used jointly or separately as the basis for the sampling plan.

Testing shall continue until no additional inoper '

able snubbers are found within a sample or until all snubbers in Tables 3.6.la and 3.6.lb have been 3/4 6-13

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT tested. The representative sample selected for testing shall include the various configurations, and the range of site and capacity of snubbers.

In addition to the regular sample, in locations where snubbers had failed the previous test due to operational or environmental conditions (exces-sive vibration, water hammer, high radiation, extreme heat or humidity, etc.), the snubbers currently installed in these locations shall be tested during the next *m t period. Test results of these snubbers may hos be included for the resampling. All replace:.at snubbers shall have been tested prior to installation.

If any snubber selected for testing either fails to lock-up or fails to move (i.e., frozen in place),

the cause will be evaluated and if caused by manufacturer design deficiency, all snubbers of the same design subject to the same defect i

shall be tested regardless of location or diffi-culty of removal. This testing requirement shall l

be independent of the requirements stated above for snubbers not meeting the test acceptance criteria.

j For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The pur-t pose of this engineering evaluation shall be to detemine if the components supported by the snubber (s) were adversely affected by the inoper-ability of the snubber (s) in order to ensure that i

the supported component remains capable of meeting the design service.

4.

Snubber Test Acceptance Criteria The snubber tests shall verify that:

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i LIMITING CONDITION FOR OPERATION SilRVEILLANCE REQUIREMENT (a) For hydraulic snubbers:

Activation (restrainingaction)isachieved within the specified range of velocity or accel-eration in both tension and compression, and snubber bleed or release rate, where required, is within the specified range in compression or tension.

(b) For mechanical snubbers:

Freedom of movement over the full range of stroke in both compression and tension is achieved.

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TABLE 3.6.1.a SAFETY RELATED HYDRAULIC SNUBBERS ACCESSIBLE /

DESIGNATION AZIMUTH INACCESSIBLE HSS #

LINE ATTACHMENT ELEVATION (East is 0*)

(A or I)

HSS-1 MS-8 A Discharge Line 32' 100*

I 2

MS-8 A Discharge Line 32' 100*

I 3

MS-8 A Discharge Line 30' 100*

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MS-8 A Discharge' Line 30' 100' I

5 MS-8 A Discharge Line 30' 100*

I 6

MS-8 A Discharge Line 30' 100*

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MS-8C Discharge Line 35' 280' I

8 MS-8 C Discharge Line 33' 280' I

9 MS-8C Discharge Line 31' 280' I

10 MS-8C Discharge Line 12' 280*

I 11 MS-8 C Discharge Line 12' 280*

I 12 MS-8C Discharge Line 5'

280*

I 13 MS-8B Discharge Line 33' 180' I

14 MS-8B Discharge f.ine 33' 180*

I 15 MS-8B Discharge Line 30' 180' I

16 MS-8B Discharge Line 30' 180*

I 17 MS-8B Discharge Line 30' 180*

I 18 MS-8B Discharge Line 30' 180*

I 19 MS-1B Supply Line 33' 200*

I 20 Recirculation Manifold 33' 90' I

21 MS-1B Supply Line 34' 260' I

22 Recirculation Manifold 32' 270*

I 23 MS-1C Supply Line 34' 140*

I 24 MS-1C Supply Line 34' 210' I

25 MS-1B Supply Line 34' 122' I

26 MS-ID Supply Line 34' 100*

I 27 MS-ID Supply Line 31' 80*

I 28 MS-1D Supply Line 31' 95*

I 29 Recirculation Manifold 32' 10' I

30 B Recirculation Fump Suction Line 3'

0' I

31 B Recirc. Pump Casing 8'

328' I

32 B Recirc. Pump Casing 8'

297*

I 33 B Recirc. Pump Casing 2'

313' I

34 A Recirculation Pump Suction Line 3'

180' I

35 A Recirc. Pump Casing 8'

148*

I 36 A Recirc. Pump Casing 8'

122' I

37 A Recirc. Pump Casing 2'

135' I

38 A Recirc. Pump Motor 19' 122' I

39 A Recirc. Pump Motor 19' 135' I

40 A Recirc. Pump Motor 19' 14E,*

I 41 B Recirc. Pump Motor 19' 297*

I 42 B Recirc. Pump Motor 19' 316' I

43 B Recirc. Pump Motor 19' 328' I

44 MS-1A Supply Line 34' 244' I

3/4 6-16

TABLE 3.6.1.a (Continued)

SAFETY RELATED HYDRAULIC SNUBBERS ACCESSICLE/

DESIGNATION AZIMUTH INACCESSIBLE HSS #

LINE ATTACHMENT ELEVATION (East is 0*)

(A or I) l 155-46 MS-1C Supply Line 34' 122' I

47 MS-3D Discharge Line 32' 122' I

48 MS-8D Discharge Line 32' 122' I

i 49 MS-8D Discharge Line 29' 122' I

50 MS-3D Discharge Line 25' 82*

I 51 MS-3D Discharge Line 25' 82*

I 52 MS-6D Discharge Line 25' 82*

I 53 MS-SD Discharge Line 10' 82' I

54 MS-3D Discharge Line 10' 82*

I 55 MS-SD Discharge Line 2'

22" I

56 MS-3D Discharge Line 2'

22' I

57 MS$D Discharge Line 2'

22' I

58 MS$D Discharge Line 2'

22' I

l 59 MS-).6 Sunolv Line 37' 262*

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61 MS3E DiscEarge Line 32' 250' I

62 MS$E Discharge Line 32' 250' I

63 MS,3E Discharge Line 35' 250' I

64 MS-6E Discharge Line 37' 250" I

65 MS,3E Discharge Line 37' 235' I

66 MS-BE Discharge Line 37' 235*

I 67 MS-GE Discharge Line 8'

270*

I 68 MS-8E Discharge Line 8'

270' I

69 MSEE Discharge Line 2'

247' I

10 MS-BE Discharge Line 2'

247' I

/1 MS-1A Supply Line 35' 277*

I 72 MS-8F Discharge Line 30' 277*

I 73 MS-BF Discharge Line 30' 277*

I 74 MS OF Discharge Line 15' 270' I

75 MS-8F Discharge Line 15' 270*

I 76 MS4F Discharge Line 12' 273' I

77 MS4F Discharge Line 12' 273' I

78 MS-8F Discharge Line 6'

272' I

79 MSSF Discharge Line 6'

272*

I 80 MS-BF Discharge Line 2'

337' I

81 MSSF Discharge Line 2'

337' I

82 MS-3E Discharge Line 12' 267*

I 83 MS-3E Discharge Line 12' 267*

I 84 MS$B Discharge Line 35' 128' I

85 MSSA Discharge Line 30' 86*

I 86 MS$A Discharge Line 30' 86*

I 87 MS$A Discharge Line 32' 82' I

88 MS$C Discharge Line 18' 215' I

89 IC-1 Supply Line 76' 20' I

90 IC-1 Supply Line 76' 20*

I 91 IC-1 Supply Line 79' 350*

I 92 IC~1 Supply Line 79' 350' I

93 IC-1 Supply Line 79' 350' I

94 IC-1 Supply Line 79' 350*

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3/4 6-17

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TABLE 3.6.1.b SAFETY RELATED MECHANICAL SNUBBERS ACCESSIBLE /

DESIGNATION INACCESSIBLE MSS #

LIhE ATTACHMENT ELEVATION LOCATION (A or I)

MSS-1 IC-2 Supply 80' Reactor Building A

2 IC-2 Supply 88' A

3 IC-2 Supply 88' A

4 IC-2 Supply 91' A

5 IC-2 Supply 91' A

6 IC-3b Supply 91' A

7 IC-3b Supply 91' A

8 IC-4a Return 85' A

9 IC-4b Return 87' A

10 IC-4b Return 77' A

11 IC-4b Return 77' A

12 IC-5 Return 77' A

13 IC-5 Return 77' A

14 C-24a Condensate 34' Condensate Bay I

15 34' I

16 34' I

17 34' I

18 34' I

19 C-24b Condensate 34' I

20 34' I

21 34' I

22 34' I

23 34' I

24 MS Drain Line 15' I

3/4 6-18

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT J.

Condensate Demineralizers J.

Coodensate Demineralizers 1.

Regeneration of a condensate demineralizing 1.

The percent of the remaining ion resin change shall occur before the unused exchange capacity of the anion resins capacity of the resin reaches a minimum shall be calculated and logged:

value of 30 pounds as chloride ions.

a.

Weekly when the influent con-2.

Anion resi6: f n the condensate danineraliz-ductivity is between 0.055 and ing system shall have a minimum salt-0.3 pmho/cm; splitting capacity of 0.75 milliequivalents per milliliter in the wet, chloride form.

b.

Daily when the influent con-Anion resins which do not have a capacity ductivity is equal to or greater of 0.75 milliequivalents per milliliter than 0.3 pmho/cm.

will be replaced with new resin as will the cation resin which occupies the same bed.

2.

Anion resins in all condensate demineralizer charges shall be 3.

At least one condensate demineralizer analyzed quarterly for salt-splitting influent conductivity instrument shall be capacity.

opera ble.

4 Whenever a demineralizer is on-line, the conductivity of either its effluent or the condensate-booster pump discharge shall be continuously monitored.

5.

Flow rate and/or integrating flow instru-mentation shall be operable and recorded for each demineralizer.

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H.

Recirculation Pump Flow Mismatch l

The LPCI loop selection logic is described in the FSAR, Section 6.P.4.2.

For some limited low probability l

accidents with the recirculation loop operating with large speed dif ferences, it is possible for the logic to select the wrong loop for injection.

For these limited conditions the core spray itself is adequate to prevent fuel temperatures from exceedinq allowable limits. However, to limit the probability even further, a procedural limitati" has been placed on the allowable variation in speed between the recirculation pumps.

The analyses fer Quad Cities indicate that above 80T power the loop select logic could not be expected to function at a 5 3eed dif ferential of 15*..

Below 80% power the loop select logic would not be expected to l

function at a speed dif ferential of 20%.

This specification provides a margin of 51', in pump speed differ-ential before a problem could arise.

If the reactor is operating on one pump, the loop select logic trips that pump before making the loop selection.

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SNUBDERS All snubbers are required OPERABLE to ensure that the structural integrity of th reactor coolant system and all other safety related systems is maintained.

Snubbers excluded from this inspection program are those installed on non-safety l

related systems and then only if their failure or failure of the system on which they are installed, would have no adverse effect on any safety related system.

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i The visual inspection frequency is based upon maintaining a constant level' of snubber protection to system',

Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval.

Any inspection whose results require a shorter inspection interval will override the previous schedule.

)

When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible, that snubber may be exempted from being counted as inoperable.

Generically sus-ceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental con-ditions such as temperature, radiation, and vibration.

B 3/4 6-10 l

s When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety related component or system has been adversely affected by the inoperability of the snubber.

The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported com-ponent or system.

To provide assurance of snubber reliability, a representative sample of the installed snubbers will be tested during plant shutdowns at eighteen (18) month intervals.

Ob-served failures of these sample snubbers shall require testing of additional 2 nits.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surveillance programs.

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Condensate Demineralizers The criteria of the resin monitoring program and the resin replacement program have been establishe j to protect the reactor from high chloride level should a seawater leak occur in the main condenser. T1ese criteria will provide for a minimum unused capacity of 30 pounds of chloride ion (50 percent depletion in a resin which is approaching the limit of 0.75 meq/ml) before a planned regeneration of a resin. Should a seawater leak occur when a resin has 30 pounds of capacity remaining, this criteria will allow a sufficient buffer for an orderly plant shutdown.

The resin depletion can be calculated using the measured salt-splitting capacity, the flow through the bed, and the average influent conductivity. Based on this result, a depletion can be calculated which will assure a 30-pound chloride ion exchange reserve. Regeneration prior to this level of depletion will assure a sufficient ion exchange reserve for removal of chloride from the condensate system.

These factors fonn the basis for the frequency of sampling, analyzing, calculation and logging surveillance requirements. Since startup of Unit 1, the salt-splitting capacity of the resins has degraded about 15%

from its initial value of 1.2 meq. A quarterly sampling frequency will be sufficient to detect the slow, long-term degradation of the resin. As conductivity increases, the calculation and logging will be increased l

to a weekly basis and ultimately on a daily basis when and if influent conductivity reaches 0.3 pmho/cm or l

greater.

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LEFT BLANK INTENTIONALLY

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