ML20040A676

Amend 81 to License DPR-21,revising Tech Specs for Inservice Surveillance of Snubbers

ML20040A676
Person / Time
Site:	Millstone
Issue date:	12/28/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:
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ML20040A675	List: ML20040A674 ML20040A676 ML20040A677 ML20040A678
References
NUDOCS 8201210401
Download: ML20040A676 (16)

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CONNECTICUT LIGHT AND POWER COMPANY,:-e? : P.

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WESTERN MA55ACHUSElI5 ELECTRIC COMPANY 7 ~ '.. c.

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NORTHEAST hUCLEAR ENERGY COMPANY Ai,2:,..':@;ff: >.

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DOCKET NO. 50-245-

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MILLSTONE NUCLEAR POWER STATION UNIT NO. 1

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AMENDMENT TO PROVISIONAL OPERATING LICENSE-k'::

hA Amendment No. 81 a -

License No. DPR.

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1.

The Nuclear Regulatory Comission (the Comission) has 'found that::

A.

The application for amendment by Connecticut Light and Power Company, The Hartford Electric Light Company, Western Massachusetts Electric Company and Northeast Huclear" Energy Company (the licensees) dated October 6, 1981, complies with.

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the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regJlations set forth in 10 CFR Chapter I; B.

The facility.will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Conr:ission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in' compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the hdalth and safety of the public; and 1

l E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

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. 2.

Accordingly, the license is amended by changes to the Technial Specifications as indicated in the attachment to this license amendment and Paragraph _ 3.8 of Provisional Operating License No. OPR-21 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A i

and B as revised through Amendment No. 81, are hereby incorporated in the license. Northeast Nuclear Energy Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h h k=

Dennis M. Crutchfield, Chief Operating Reactors Branch d5 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 28, 1981

ATTACHMENT TO LICENSE AMENDMENT N0. 81 PROVPjIONAL OPERATING LICENSE NO. DPR-21 DOCKET NO. 50-245 Replace the attached pages* of'the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the drea of change.

Remove Insert 3/4 6 3/4 6-16 3/4 6 3/4 6-16 3/46-17-3/46-19**

B3/4 6 B3/4 6-12 B3/4 6 B3/4 6-12

• 0verleaf pages 3/4 6-11 and B3/4 6-9 are also included.

• • Paginrtion change only on 3/4 6-19.

m LIMITING CONDITION FOR OPERATION SilRVEILLANCE REQUIREMENT 2.

If Specification 3.6.H.1 cannot be met,

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one recirculation pump shall be tripped.

Operation with a single recirculation pump is permitted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the recir-culation pump is sooner made operable.

If the pump cannot be made operable, the reactor shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.

The reactor shall not be operated unless the equalizer valves are closed.

4.

With the mode switch in the startup/ hot standby or run mode, operation without forced circulation shall not be permitted.

u Amendment No. 1%,34 November 19, 1976 3/4 6-11

SURVElllANCE REQUIREKENT LIMITING CONDITION FOR OPERATION 3.6.I SNUBBERS 4.6.I SNUBBERS

1. The snubbers listed in Tables 3.6.1.a and Each snubber shall be demonstrated OPERABLE by preform-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 inspected 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 pemissible only ra Du during the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following such detemination c

r ing Next Required unless the snubber is sooner replaced, made oper-Inspection Interval Inspection Interval able, or an engineering evaluation determined 0

18 morths i 25%

the supported system / component to be operable 1

12 months i 25%

with the inoperable snubber.

2 6 months i 25%

4. If the requirements of 3.6.I.2 and 3.6.1.3 cannot 3,4 124 days i 25%

be met, an orderly shutdown shall be initiated and within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

-h6,7.

i the reactor shall be in a cold shutdown condition The required inspection interval shall not be l

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

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

subgroups; those accessible and those inaccessible

6. Snubbers may be added to or deleted from safety ouring reactor operation. Each group and subgroup related systems without prior License Amendment 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 are provided in accordance with 10 CFR 50.59 and that a proposed revision to Tables 3.6.1.a and 3.6.1.b is included with the next 1.icense Amend-ment Request.

3/4 6-12 Amendment No. J0, #7, 81 l

SilRVE!LLANCE REQUIREMENT f

LIMITING CONDITION FOR OPERATION 2.

Visual Inspection Acceptance Criterja j

Visual inspections shall be conducte6 'in the f0llowing mannert (c)inthecasewherethe 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 suscertible; or (b) if there are visual indications of esmage 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 detennined 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 4.6.1.4b as applicable, an additional 10% 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 Amendment No. 81 3/4 6-13

LIMITING CONDITION FOR OPERATION SilRVEILLANCE REQUIREMENT tested. The representative sample selected for testing shall include the various configurations, and the range of size 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 test period. Test results of these snubbers may not be included for the resampling. All replacement 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 shall be tested regardless of location or diffi-culty of removal. This tssting requirement shall be independent of the requirements stated above

'for snubbers not meeting the test acceptance criteria.

For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s). The pur-pose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoper-ability of the snubber (s) in order to ensure that the supported component remains capable of meeting the design service.

4.

Snubber Test Acceptance Criteria knendment No. 81 The snubber tests shall verify that:

3/4 6-14 mm

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

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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..

,e.

(b) For mechanical snubbers:

The force that initiates and maintains free movement of the snubber rod in either tension or compression is less than the specified maximum drag force; and activation (restraining action) is achieved within the specified range in compression and tension.

• Functional tests for mechanical snubbers as stated above will not be performed until such time that suitable on-site testing equipment is procured.

In the interim, a stroke tes,t will be performed to verify freedom of movement over the full range of stroke in both compression and tension.

Amendment No. 81

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3/4 6-15

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TABLE 3.6.I.a SAFETY RELATED HYDRAULIC SNUBBERS ACCESSIBLE /

DESIGNATION AZIMUTH INACCESSIBLE HSS #

LINE ATTACHMENT ELEVATION (East is 0*)

(A or I)

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

I 2

MS-8;; Discharge Line 32' 100*

I 1

MS-8 A Discharge Line 30' 100*

I 4

MS-8 A Discharge' Line 30' 100*

I 5

MS-8 A Discharge Line 30' 100*

I 6

MS-B A Discharge Line 30' 100*

I 7

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-8 C Discharge Line 12' 280*

I 11 MS-8C 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 Line 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-18 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' 21 0' I

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

26 MS-10 Supply Line 34' 100*

I 27 MS-1D Supply Line 31' 80' I

28 MS-1D Supply Line 31' 95*

I 29 Recirculation Manifold 32' 10' I

30 B Recirculation Pump Suction Line 3'

0' I

31 B Recirc. Pump Casing 8'

328' I

32 B Retirc. 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 Retirc. Pump Motor 19' 122' I

39 A Recirc. Pump Motor 19' 135' I

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

I 41 B Recirc. Pump Motor 19' 297*

I 42 8 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 Amendment No. 81

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TABLE 3.6.I.a (Continu;d)

SAFETY RELATED HYDRAULIC SNUBBERS ACCESSIBLE /

SESIGNATION AZIMUTH

'INACCESSIEE HSS #

LINE ATTACHMENT ELEVATION (East is O*)

(A or I) 455-46 MS-1C Supply Line 34' 122' I

47 MS-BD Discharge Line 32' 122' I

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48 MS-80 Discharge Line 32' 122'

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

50 MS-BD Discharge Line 25' 82*

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

I 52 MSSD Discharge Line 25' 82' -

I 53 MS-SD Discharge Line 10' 32' I

54 MS-3D Discharg.e Line 10' 62*

I 55 MS-3D 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 Lire 2'

22' I

59 MS-1B Sucoly Line 37' 262*

I 61 MS$E DiscEarge Line 32' 250' I

62 MS$E Discharge Line 32' 250*

I 63 MS 3-Discharge Line 35' 250' I

64 MS-a : Dischatge Line 37' 250*

I 65 MS'8E Discharge Line 37' 235' I

66 MS-BE Discharge Line 37' 235' I

67 '

MS BE Discharge Line 8'

-270' I

68 MS-8E Discharge Line 8'

270' I

69 MSSE Discharge Line 2'

247' I

70 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-8F Discharge Line 15' 270*

I 75 MS-8F Discharge Line 15' 270' I-76 MS-8F Discharge Line 12' 273*

I 77 MS-BF Discharge Line 12' 273*

I 78 MS-BF Discharge Line 6'

272*

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79 MSSF Discharge Line 6'

272*

I 80 MS-3F Discharge Line 2'

337' I

81 MS$F 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

MS A Discharge Line 30' 86*

I 85 MS A Discharge Line 30' 86*

I 86 87 MS$A Discharge Line 32' 82' I

MS C Discharge Line 18

215" I

88 89 IC-1 Supply Line 76' 20*

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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' I

3/4'6-17 Amendment No. 81 l

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TABLE 3.6.1.b SAFETY RELATED MECHANICAL SNUBBERS

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ACCESSIBLE /

DESIGNATION INACCESSIBLE MSS #

,LINE 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

91' A

4 IC-2 Supply

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91' A.

5 IC-2 Supply 6

IC-3b Supply 91' A

7 IC-3b Supply 91' A

8 IC-4a Return 85' A

A 9

IC-4b Return 87' 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

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22 34' I

23 34' I

24 MS Drain Line 15' I

l 3/4 6-18 Amendment No. 81 T

SURVEILLANCE REQUIREMENT LIMITING CONDITION FOR OPERATION J.

Condensate Demineralizers J.

Condensate Demineralizers i

1.

The percent of the remaining fon 1.

Regeneration of a condensate demineralizing exchange capacity of the anion resins resin change shall occur before the unused shall be calculated and logged:

capacity of the resin reaches a minimum value of 30 pounds as chloride ions.

Weekly when the influent con-a.

ductivity is between 0.055 and 2.

Anton resins in the condensate demineraliz-0.3 pmho/cm; ing system shall have a minimum salt.

splitting capacity of 0.75 mil 11 equivalents b.

Daily when the influent con-per milliliter in the wet, chloride form.

ductivity is equal to or greater Anion resins which do not have a capacity than 0.3 pmho/cm.

of 0.75 milliequivalents per milliliter will be replaced with new resin as will the 2.

Anion resins in all condensate cation resin which occupies the same bed.

demineralizer charges shall be I

analyzed quarterly for salt-splitting 3.

At least one condensate demineralizer influent conductivity instrument shall be capacity.

opera bl e.

4.

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

Flow ' ate and/or integrating flow instru-5.

r mentation shall be operable and recorded for each demineralizer.

3 n

4 knendmenti.No. 81 3/4 6 19 9

The following factors form the basis for the surveillance require 1ents:

A break in a jet pump decreases the flow resistance charactcr?stic of the external piping loop causing the recirculation pump to operate at a higher flow condition when compared with previous operation ~.

The change in flow rate of the failed jet pump produces a change in the-indicated flow rate of that pump relative to the other pumps in that loop.

Cwnparison of the data with a normal relationship or pattern provides the indication necessary to detert a failed jet pump.

The jet pump flow deviation pattern derivod from the diffuser to lower plenum dif ferential pressure readings will be used to further evaluate jet pump operability in the event that the jet pumps fail the tests in Sections 4.6.G.1 and 2.

Agreement of indicated core flow with established power-core flow relationships provides the most assurance that recirculation flow is not bypassing the core through inactive or broken jet pumps. This bypass flow is reverse with respect to normal jet pump flow. The indicated total core flow is a summa-tion of the flow indications for the twenty individual jet pumps. The total core flow measuring instrumentation sums reverse jet pump flow as though it were forward flow. Thus, the indicated flow is higher than actual core flow by at least twice the n6rmal flow through any backflowing pump. Reactivity inventory is known to a high degree of confidence so that even if a jet pump failure occurred during a shutdown period subsequent power ascensinn would promptly demonstrate abnormal control rod withdrawal for any power-flow operating map point.

A nozzle-riser system failure could also generate the coincident failure of a jet pump body; however, the converse is not true. The lack of any substantial stress in the jet pump hody makes failure impossibl e.

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B 3/4 6-9 ;

H.

Recirculation Pump Flow Mismatch The LPCI loop selection logic is described in the FSAR, Section 6.7.4.2.

For some limited low probability accidents with. the recirculation loop operating with large speed differences, it is possible for the logic to select the wrong loop for injection.

i for these limited conditions the core spray itself is adequate to prevent fuel temperatures from exceeding l

allowable limits. However, to limit the probability even further, a procedural limitation has been placed l

on the allowable variation in speed between the recirculation pumps.

The analyses for Quad Cities indicate that above 80% power the loop select logic could not be expected to function at a speed differential of 15%.

Below 80% power the loop select logic would not be expected to function at a speed differential of 20%. This specification provides a margin of 5% 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.

I.

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

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

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems.

Therefore, the required inspection interval varies inversely with the observed snubber failures and is determined by the ntimber 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 und 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 Amendment.No. J0, AJ, 81

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 units.

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

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Condensate 0emineralizers The criteria of the resin monitoring program and the resin replacement program have been established to protect the reactor from high chloride level should a seawater leak occur in the main condenser. These 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 condensat.e 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 to a weekly basis and ultimately on a daily basis when and if influent conductivity reaches 0.3 pmho/cm or greater.

B 3/4 6-11 Amendment No. J0, JJ, 81

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LEFT BLANK INTENTIONALLY l

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l B 3/4 6-12 Amendment No. 81