ML20052F751

Amends 70,62,76 & 70 to Licenses DPR-19,DPR-25,DPR-29 & DPR-30,respectively,modifying Tech Specs to Provide Addl Surveillance Requirements for safety-related Hydraulic & Mechanical Snubbers

ML20052F751
Person / Time
Site:	Dresden, Quad Cities, 05000000
Issue date:	04/28/1982
From:	Crutchfield D, Vassallo D Office of Nuclear Reactor Regulation
To:	Commonwealth Edison Co, Iowa Illinois Gas & Electric Company
Shared Package
ML20052F752	List: ML20052F751 ML20052F758 ML20052F764
References
DPR-19-A-070, DPR-25-A-062, DPR-29-A-076, DPR-30-A-070 NUDOCS 8205130572
Download: ML20052F751 (53)

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UNITED STATES

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g NUCLEAR REGULATORY COMMISSION g

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COMM0t: WEALTH EDISON COMPANY DOCKET N0. 50-237 DRESDEN STATION UNIT N0. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Air.endment No. 70 License No. DPR -19 1.

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

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated April 16, 1981 as supplemented by letter dated September 29, 1981, complies with the standards and requ.rements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations 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 Commission; C.

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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security-or to the health and safety of the public; and 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.

2.

Accordingly, the license is amended by changes to the Technical

~

Specifications as indicated in the attachment to this license amend-ment, and paragraph 3.8 of Provisional License ~ No. DPR-19 is hereby amended to read as follows:

l B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 70, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

8205130572 820428 PDR ADOCK 05000237 P

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

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FOR THE NUCLEAR REGULATORY CO M ISSION fOnea M &

Dennis M.'Crutchfield, ief Operating Reactors Branch #5 Division of Licensing

Attachment:

i Changes to the Technical Specifications Date of Issuance: April 28, 1982 2-i i

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3.6 LIMITING CONDITION FOR OPERATION DP R-19 '

/4.6- $URVEILLANCE REQUIREMENT ;

The required inspectiori interval shall not be lenthened nors;than orie st.ep at a time.

c Snubbers may be categorized in two groups, " accessible"

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or " inaccessible," based on their accessibility for inspection during reactor operation. These two groups may be inspected independently according to thi above schedule.

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2.

Functional Testing a.

Once each refuuing. cycle, a representative sample of approximately 10% of the hydraulic snubbers con-

, tained in Table 3.6.la shall be functionally tested for operability,. including:

• (i) Activiation (restraining action) is achieved within the specified range of velocity or acceleration in tioth tension.and compression.

• (ii) Snubber bleed, or release. rate, where required, is within the specified range in-compression or tension.

• NOTE : Paragraphs (i) and (ii) shall not becomo effective until competitive marketable test fixtures are available.

Until such time, but in no case to exceed 12/31/83, demonstration of snubber bleed, or release, shall be sufficient.

For each unit and subsequent, unit found inoperable, an additional 10% of the hydraulic snubbers shall be tested until no more failures are found or all units have been tested.

I b.

Once each refueling cycle, a representative sample I

of approximately 10% of the mechanical snubbers con-tained in Table 3.6.lb shall be functionally tested for operability. The test shall consist of two parts:

• • (i)

Verification that the force that initiates free movement of the snubber in either ten-sion or com;"ession is less than the speci-fied maximum breakaway friction force.

• • (ii)

Verify that the activation (restraining action) is achieved within the specified range of acceleration in both tension and compression.

• • NOTE: Paragraph (ii) shall not become effective until competitive marketable test fixtures are available.

Amendment No. 70 Until then,but in no case to exceed 12/31/83, the functional test will be limited to only paragraph (1).

9

DPR-19 3.6 LlHITING CONDITION FOR OPERATION k.6 SURVEILLANCE REQUIREMENT For each unit and subsequent unit found in-operable, an additional 10% of-the mechanical snubbers shali be so tested until no more failures are found or all units have been l

tested.

I In addition to the regular sample, snubbers c.

which failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snocbers may not be included for the resampling.

3.

When a snubber is deemed inoperable, a review of all pertinent facts shall be conducted to deter-mine the snubber mode of failure and to decide if an engineering evaluation should be performed on the supported system or components.

If said evaluation is deemed necessary, it will determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

4.

If any snubber selected for functional testing either fails to lock up or fails to move, i.e.,

frozen in place, the cause will be evaluated and, if determined to be a generic deficiency, all snubbers of the same design subject to the same defect shall be functionally tested.

5.

Snubber service life monitoring shall be followed by existing station record systems, including the

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central-filing system, maintennuce files, safety related work packages, and snubber inspection records. The above record retention methods shall be used to prevent the hydraulic anubbers from exceeding a service life of 10 years and the snechanical snubbers from exceeding a service life of 40 years (lifetime of the plant).

91c-1

TABLE 3.6.lb (Continued)

SAFETY RELATED HECilANICAl. SNUBBERS SNUDDERS SHUBBERS SNUBBER IN ll!Gli INACCESSIBLE ACCESSIDLE SHUBBER 1.0 CAT 10N ELEVATION A7.IHUTil RADIATION AREA DURING NORMAL DURING HORMAL Ho.

DURING SilUTDOWN OPERATION OPERATION 37 Drywell Recire. Line 2014-28" 518' 90 X

X 38 Drywell_ Shutdown Cooling Line 1001A-16" 523' 0*

X X

39

ywell Rx Water Cleanup Line 1201-8" 533' 316*

X X

40 Drywell Rx Water Cleanup Line 1201-8" 533' 30!*

X X

41 Drywell Main Steam Line 3091B-20" 534' 28*

, X X

42 Drywell Hain Steam Line 3001A-20" 536' 14*

X X

43 Drywell Hain Steam Line 3001D-20" 536' 346*

X X

44 Drywell Main Steam Line 3001C-20" 536' 332*

X X

• 45 Drywell Main Steam Line 3001B-20" 545' 105*

X X

46 Drywell Main Steam Line 30018-20" 543' 105*

X X

47 Drywell Main Steam Line 3001A-20" 542' 73*

X X

48 Drywell Main Steam Line 3001A-20" 543'6" 73*

X X

49 Drywell Main Steam Line 3001A-20" 539' 20*

X X

50 Drywell Hain Steam Line 3001C-20" 543'6" 195*

X X

51 Drywell Main Steam Line 3001C-20" 542' 195*

X X

52 Drywell Hain Stdam Line 3001D-20" 543' 343' X

X 53 Drvwell Hain Steam Line 3001D-20" 544' 343' X

X Hodifications to this table due to changes in high radiation should be submitted to the NRC as part of the next liccuse amerdment request.

Amendment No. 70 91e-2 DPR-19 i

i DPR-19 11. Recirculation Pump Flow Hiematch cn earthquake or severe transient while allowing normal thermal motion during startup and shutdown.

The LPCI loop selection logic has been described in The consequence of an inoperable snubber is an in -

the Dresden Nuclear Power Station Units 2 and 3 crease in the probability of structural damage to FSAR, Amendments 7 and 8.

For some limited low piping as a result of a seismic or other eveat probability accidents with the recirculation loop initiating dynamic loads.

It is therefore required

+

operating with large speed differences, it is pos-that all snubbers required to protect the primary eible for the logic to select the wrong loop for coulant system or any other safety system or cum-injection. For these limited conditions, the core ponent be operable during reactor operation, spray itself is adequate to prevent fuel tempera-tures from exceeding allowable limita. Ilowever, Because the snubber protection is required only to limit the probability even further, a procedural during low probability events, a period of 72 linitation has been placed on the allowable vari-hours is allowed for repairs or replacements.

In etion in speed between the recirculation pumps.

case a shutdoun 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 per-The licensee's analyses indicate that above 80%

mit an orderly shut.down consistent uith 4tandard power the loop select logic could not be expected operating procedures. Since plant startup should to function at a speed differential of 15%. Below not commence with knowingly defective safety re-80% pover, the loop select logic would not be ex-lated equipment, Specif icat ion 3.6.1.4 prohibits pected to function at a speed differential of 20%.

startup with inoperable snubbers.

This specification provides a margin of 5% in pump speed differential before a problem could arise.

When a snubber is found inuperable, a review shall If the reactor is operating on one pump, the loop be performed to determine the snubber mode of select logic trips that pump before making the failure. Results of the review ahali. be used to icop selection.

determine if an enuineerinu evaluation of the safety-related system or component is necessary. The In addition, during the start-up of Dresden Unit 2, engineering evaluation shall deterr.ine whether or it was found that a flow mismatch between the two not the snubber node of failure has imparted a signi-acts of jet pumps caused by a difference in re-ficant effect or degradation on the support component circulation loops cculd set up a vibration until or system.

a nisnatch in speed of 27% occurred. The 10% and 15* speed misustch restrictions provide additional All safety related hydraulic snubbers are visually margin before a pump vibration problem will occur.

inspected for overall integrity and operability.

The inspection vill include verification of proper ECCS performance during reactor operation with one orientation, adequate hydraulic fluid level and recirculation loop out of service has not been proper attachment of snubber to piping and structs.es, analyzed. Therefore, sustained reactor operation under such conditions is not permitted.

All safety related mechanical snubbera are visu-ally inspected for overall integrity and opera-1.

Snubbers (Shock Suppressors) bility. The inspection will include verification of proper orientation and attachments to the piping Snubbers are designed to prevent unrestrained pipe and anchor for indications of damage or impaired motion under dynamic loads as might occur during operability.

Amendment No. 70 99a 9

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DPR-19 v\\

The inspection frequency is based upon maintaining a When the cause of rejection of the snubber is constant level of snubber protection.

Thus, the re-clearly established and remedied for that snubber quired inspection interval varies inversely with the and for any other snubbers that may be generically observed snubber failures. The number of inoperable susceptible, and verified by inservice functional snubbers found during a required inspection deter-testing, that snubber may be exempted from being mines the time interval for the next required in-counted as inoperable. Generically susceptible spection.

Inspections performed before that interval snubbers are those which are of a specific make or has elapsed may be used as a new reference point to model and have the same design features directly determine the next inspection, llowever, the results related to rejection of the snubber by visual in-of such early inspections performed before the spection or are similarly located or exposed to original require time interval has elapsed (nominal the same environmental conditions such as tempera-time less 25%) may not be used to lengthen the re-ture, radiation, and vibration, quired inspection interval. Any inspection whose results require a shorter inspection interval will Monitoring of snubber service life shall consist override the previous schedule, of the existing station record systems, including the central filing system, maintenance files, To further increase the assurance of snubber re-safety-related work packages, and snubber inspection liability, functional tests will be performed once records. The record retention programs employed at each refueling cycle. A representative sample of the station shall allow station personnel to main-10% of the safety-related snubbers will be func-tain snubber integrity. The service life for tionally tested. Observed failures on these samples will require testing of additional units.

hydraulic snubbers is 10 years. The hydraulic snubbers existing locations do not impose undue Ilydraulic snubbers and mechanical anubbers may each safety implications on the piping and components be-cause they are not exposed to excesses in environ-be treated es different entities for the above mental conditions. The service life for mechanical curveillance programs.

anubbers is 40 years, lifetime of the plant. The mechanical snubbers are installed in areas of harsh Ilydraulic snubber testing will include stroking of environmental conditions because of their dependa-the snubbers to verify piston movement, lock-up, bility over hydraulic anubbers in these areas. All and bleed.

Functional testing of the mechanical snubber installations have been thoroughly engineered snubbers will consist of verification that the providing the necessary safety requirements. Evalua-force that initiates free movement of the snubber tions of all snubber locations and environmental in either tension or compression is less than the conditions justify the above conservative snubber maximum breakaway friction force. The remaining service lives, portion of the functional test consisting of veri-fication that the activation (restraining action) is achieved within the specified range of accelera-tion in both tension and compression will not be done.

This is due to the lack of competitive marketable test fixtures available for station use.

Therefore, until such time as test fixtures become available, only part (i) of the test will be per-formed; part (ii) will not be done.

Amendment No. 70 99b 1

3.7 LINITING CONDITION FOR OPERATION 4.7 SURVEILLANCE REQUIREMENTS 2.

Primary containment integrity stealt be maintained 2.

Tl primary containment integrity shall be desson-at all times when the reactor is critical or when 0

the reactor water temperature is above 212*F and strated by conducting Primary Containment Leak fuel is in the reactor vessel except wirile per-Teste and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 4

forming low power physics tests at atmospheric using the methods and references therein.

pressure at power levele not to exceed 5 Hw(t).

a.

Three Type A teste (Overall Integrated Con-s.

Primary containment leakage rates are defined tainment Leakage Rate) shall be conducted at i

from:

8 approximately equal intervale during each 10 year plant in-service-inspection interval at (1) The calculated peak containment internal either P, or P with the last being done t

pressure P, is equal to 48 peig.

during the 10 year in-service inspection shut-down.

(2) The containment vessel reduced test-pressure, P, la equal to 25 peig.

b.

If any periodic Type A test falls to meet g

either 75 percent of L. or 75 percent ~of L.

(3) The maximum allowable leakage rate at t

a the test schedule for subsequent Type A tests pressure of P,, L, is equal to 1.6 shall be reviewed and approved by the Commission, percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 48 peig.

If two consecutive Type A teste fail to meet c.

either 75 percent of L, or 75 percent of Lg,

- (4) The maximum allowable test leakage rate at a a Type A test shall be performed at each shut-pressure of Pg, Lt.is less than or equal to down for refueling or approximately every la La (Ltm/ Lam).

If Ltm/ Lam is greater than 0.7, months until two consecutive Type A testa le (specified as equal to) La (P /P )b.

Lt t a meet the above requirements, at which time the normal test schedule may be resumed.

(5) The total measured leakage rates at A

l pressures of P, and pg are Lam tm, d.

l and L respectively.

he accuracy of each Type A test shall be verified by a supplemental test which:

j

=

l b.

When primary containment entegrity is re-(1) Confirms the accuracy of the test by quired, primary containment leakage rates verifying that the difference between shall be limited to:

the supplemental data and the Type A test data (1) An overall integrated leakage rate for is within 25 percent of La or Type A teste of:

25 percent of L.'

t (2)

(a) Lam less than or equal to 75 per-lies a duration suf ficient to establish cent of L..

accurately the change in leakage rate between the Type A test and the supple-mental test.

(b)

L. less than or equal to 75 per-t cent of L.

t Amendment No.

70

'109

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3.7 LIH1TlHC COHOITION FOR OPERAT10ll 4.7 SURVEILLANCE REQU1HEHENTS

' (2)

(a) A combined leakage rate of Ices tiian

.(3) Requires time c,uant ity of gas injected -

or equal to 60 percent of Le for all into the containment or bled from the testable penetrations and isolation containmenit during the supplemental test

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valves subject to Type B and C teste to be equivalent to at least 9 sc fm.

6 except for main steam isointioni valves.

e. ' Type B and C teste alia11 be conducted at Fa.

(b) A leakage rate of less than or equal at Intervale no greater than 24 months except to 3.75 percent of La for any one for teste involving:

a air lock when pressurized to 10 peig.

(1) Hain eteen !!ne teolation valves wielch (c) 11.5 SCF per hour for any main steam shall be tested at a pressure of 25 pels isolation valve at a test pressure of each operating cycle.

25 peig.

(2) Bolted double gasketed seale which shall be tested at a pressure of 48 pelg when-ever time seal la clos 2d af ter being opened and each operating cycle.

t (3) Air locks wlitch shall be tested at 10 pels each operating cycle.

f.

Continuous Leak Rate Honitor (1) llhen the primary containment le inertede the containeesat elia.. be continuously

' monitored for grose leakage by review of the inerting system make-up require-mente.

i (2) This monitoring system may be taken out i

of service for the purpose of maintenance or testing but shall be returned to service as soon as practical.

g.

The interior surfaces of the drywell shall be vleuelty inspected encle operating cycle for evidence of deterioration.

4 a

Amendment'No. 70 110

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g NUCLEAR REGULATORY COMMISSION 5

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I C0tHONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEfl STATION UNIT NO. 3

_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 62 License No. DPR 1.

The Nuclear Regulatory Conmission (the Conmission) has found that:

A.

The application for amendment by the Comonwealth Edison Company (the licensee) dated April 16,1981 as supplemented by letter dated September 29, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 Connission; C.

There is reasonable assurance (i) that the activities a~uthorized 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 Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragraph 3.B of Facility Operating License No. DPR-25 is hereby amended to read as follows:

4 B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.62, are hereby incorporated in the license.

The licensee 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 Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to-the Technical Specifications Date of Issuance: April 28,1982 i

I

-. ~.

r ATTACHMENT TO LICENSE' AMENDMENT-NO. 62 t

FACILITY OPERATING LICENSE NO. DPR-25

-1 DOCKET NO. 50-249 Revise the Appendix "A" Technical Specifications as follows:

c Remove Replace 91b 91b 91c 91c l

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91d-2 j

91e 91e-1 91e-2 99a 99a 99b 99b i

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ppm-25 3.6 LilitTit*G CONDITION FOR OPERATION 4,6 8URVttlLilHCE REQUIREHENT I,

Snubbers (Shock Suppressors)

I.

Snubbere (Shock Suppressors) 1.

During all modus of operation escept cold shut-The following autveillance requirements apply to all down and refuel, all safety related snubbers safety telated snubbers listed in Tables 3.6.laand{

linted in Table 3.6.la and 3.6.lb shall be oper-3.6.lb.

able creept as noted in Specification 3.6.1.2 thr., ugh 3.6.1.4.

1.

Visual Inspection 2.

From and after the time a anubber is determined An independent visual inspection shall be per-to 1,e inoperable, continued reactor operation is formed on the safety related hydraulic and permissible only during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> mechanical snubbers contained in Tables 3.6.la unless the snubber is sooner made operable or and 3.6.lb in accordance with the below schedula replaced.

a.

All hydraulic enubbers whose seal material 3.

11 t he requirement s of 3.6.1.1 and 3.6.1.2 can-has been demonstrated by operating exper-not be met, an orderly sleutdown a, hall be ini-ience, lab testing or analysia to be com-tiated and the reactor shall be in cold shutdown patible with the operating envirunn.ent or refuel condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

shall be visually inspected. This inspec-tion shall include, but not necessarily be 4.

If a anubbar is determined to be inoperable limited to, inspection of the hydraulic e

while the reactor is in the cold shutdown or re-fluid reservoir, fluid connections, and fuel mode, the snubber shall be made operable or IInkage connection to the piping and anchor replaced prior to reactor startup, to verify snubber operability.

5.

Snubbers may be added to safety related systeas b.

All mechanical snubbers shall be visually without prior license amendment to Tables inspected. This inspection shall consist 3.6.la and/or 3.6.lb provided that a revision of, but not necessarily be limited to, in-tu T. ables 3.6.la and/or 3.6.lb is included with spection of the snubber and attachments to license annendment request.

the piping and anchor for indications of the next deinage or impaired operability.

No. of Snubbers Found Inoperable During Next Required Inspection Interval Inspection Interval 0

18 months + 25%

12 months T 25%

2 6 months I 25Z 3, 4 124 days T 25%

5, 6, 7 62 days

[25%

• ,;, p 62

+8 31 days 1 25%

wn er,-

91b

3.6 LIMITING CONDITION FOR OPERATION 0?R-25 4.6 SURVEILLANCE REQUIREMENT The required inspection interval shall not be lenthened more than one step at a time.

Snubbers may be categorized in two groups, " accessible" or " inaccessible," based on their accessibility for inspection during reactor operation. These two groups may be inspected independently according to the above schedale.

2.

Functional Testing a.

Once each refueling cycle, a representative sample of approximately 10% of the hydraulic snubbers con-tained in Table 3.6.la shall be functionally teste:

for operability, including:

• (i) Activiation (restraining action) is achieves within the specified range of velocity or acceleration in both tension and compression.

• (ii) Snubber bleed, or release rate, where required, is within the specified range in compression or tension.

• NOTE : Paragraphs (i) and (ii) shall not become effective until competitive marketable test fixtures are available. Until such time, but in no case to exceed 12/31/83, demonstration of snubber bleet, or release, shall be sufficient.

For each unit and subsequent unit found inoperable, an additional 10% of the hydraulic snubbers shall be teste:

until no more failures are found or all units have been tested.

b.

Once each re#ueling cycle, a representative sample of approximately 10% of the mechanical snubbers con-tained in Table 3.6.lb shall be functionally tested for operability. The test shall consist of two parts:

• • (1) Verification that the force that initiates free movement of the snubber in either ten-sion or compression is less than the speci-fied maximum breakaway friction force.

• • (ii) Verify that the activation (restraining action) is acnieved within the specified range of acceleration in both tension and compression.

• • NOTE: Paragraph (ii) shall not become effective until Arendment No. 62 competitise marketable test fixtures are availatie.

Until then,but in no case to exceed 12/31/ 83, the functional test will be limited to only paragraph (1).

6

DPR-25 3.6 LlHITlHC CONDITION FOR OPERATION 4.6 SURVEll. LANCE REQUIREMENT For each unit and subsequent unit found in-l operable, an additional 10% of the mechanical I

snubbers shall be so tested until no more failures are found or all units have been tested.

c.

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be included for the resampling.

1 3

3.

When a snubber is deemed inoperable, a review of all pertinent facts shall be conducted to deter-mine the snubber mode of failure and to decide f

if an engineering evaluation should be performed on the supported system or components.

If said evaluation is deemed necessary, it will determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

4.

If any snubber selected for functional testing either fails to lock up or fails to move, i.e.,

frozen in place, the cause will be evaluated and, t

if determined to be a generic deficiency, all 4

snubbers of the same design subject to the same defect shall be functionally tested.

5.

Snubber service life monitoring shall be followed by existing station record systems, including the central filing system, maintenance files, safety related work packages, and snubber inspection records. The above record retention methods shall be used to prevent the hydraulic snubbers from exceeding a service life of 10 years and the mechanical snubbers from exceeding a service life of 40 years (lifetime of the plant).

91c-1 1

TABLE 3.6.la SAFETY RELATED llYDRAULIC SNUBBERS SNUB 3ERS SNUBBERS SNUBBER ' IN !!ICll INACCESSIBLE ACCESSIBLE SNUBBER LOCATION ELEVATION AZIMUTil RA91ATION AREA DURINC N010tAL DURINC NORMAL I;0.

DURING SilDTDOWN Ol>!GtATION Ol'ERATION 2

Torus Ring fleader 1501-24" 483'

,83*

X 3

Torus Ring lleader 1501-24" 483' 74*

X 4 -

4 Torus Ring lleader 1501-24" 483' 38*

X 5

Torus Ring lleader 1501-24" 483' 29' X

7 Torus Ring liender 1501-24" 483' 331*

X 8

Torus Ring !!eader 1501-24" 483' 322*

X 9

Torus Ring lleader 1501-24" 483' 286*

X, 10 Torus Ring lleader 1501-24" 483' 277*

X I

12 Torus Ring lleader 1501-24" 483' 218' X

13 torus Ring !!cader 1501-24" 483' 209*

X 4

15 Torus Ring lleader 1501-24" 483' 151*

X b

16 Torus Ring lleader. 1501-24" 483' 142' X

t I

I

,* Modifications to this table due to changes in high radiation should be submitted to the llRC as part of-the next license l emendment request.

Amendment No. 62 DPR 25 91d-l

TABLE 3.6.la (Continued)

SAFETY RELATED llYDRAULIC SNUBBERS l

SNUBBERS SNUDBERS SNUBBER IN stICll

• INACCESSIBLE ACCESSIBLE St1UBBER LOCATIOtt ELEVATION A7.IMUTit RADIATION AREA DURI!!G N0lutAL DURING NORt!AL 11 0.

DURIt1C SilUTDOWN OPERATION OPERATION Isol tion Condenser Pipeway Room:

1 Isolation condenser Line 1303-12" 558' 180*

X X

2 Isolation condenser Line 1303-12" 568' 180*

X X

3 Isolation Condenser Line 1302-14" 580' 195*

X X

\\

j 1

I

• Modifications to this table due to changes in high radiation should be submitted to the !!RC as part of the next license amendment request.

Amendment No. 62 npo _x 91d-2

TABl.E 3.6.lb SAFETY RELATED MECllANICAL SNUBBERS l

SNUBBERS SNUBDEltS SNUBBER IN 111C11 INACCESSIBLE ACCESSIBLE SIIUBUER LOCATION ELEVATION AZlHUTil RADIATIO.1 AREA DURING t:0RflAL DURit:0 NORitAL NO.

DURING SilUTDOWN OPERATIO11 OPERATION 1

Drywell Res. ire. Motor 3D-202 524' 328*

X X

2 Dryuell Recire. Motor 3B-202 524' 302*

X X

3 Drywell Recire. Motor 3B-202 524' 315*

X X

4 Drywell necire. Motor 3A-202 524' 148*

X X

5 Dryuell Recirc. Motor 3A-202 524' 122*

X X

6 Drywell Recire. Ilotor 3A-202 524' 135*

X X

7 Drywell Recire. Pump 311-202 512' 326*

X X

8 Drywell Recirc. l'un.p 311-202 512' 304*

X X

9 Dryuell Recire. Pump 33-202 507' 315*

X X

10 Dryue11 Rucirc. Pump 3A-202 512' 124*

X X

11 Dryuell Recire. Pump 3A-202 512' 146*

X X

12 liryucIl Recirc. Pun.p 3A-202 507' 135*

X X

13 Removed 14 Removed 15 Dryuell Ll*C1 Line 1506-16" 513' 256*

X X

16 Dryuell LPCI Lin : 1519-16" 513' 95*

X X

17 Removed 18 19 20 i

21 Dryuell Recire. lleader 201A-22" 533'6" 22*

X X

1 22 Dryucll llPCI Line 2305-10" 550' 121*

X X

• Modifications to this table due to changes in high radiation should be submitted to the IIRC as part of the next license cmendment request.

A.nendment No. 62 opH-25 91e-1

TABl.E 3.6. lb (Continued)

SAFETY RELATED MECllANICAL SNUBBERS l

SNUBBERS SNUBBERS SNUBBER IN 111C11 INACCESSIBLE ACCESSIBLE SilUBUER LOCATION ELEVATION AZittuTil RADIATION AREA DURINC NOR}lAL DURlt!C NORtlAL NO.

DURING SilUTDolitt OPERATI0tt OPEllATION 23 Drywell Cleanup Line 1201-8" 537'6" 84*

X X

24 Removed 25 Drywell Cleanup Line 1201-8" 537'6" 78*

X X

26 Removed f'

27 Drywell Cleanup 1.ine 1201-8" 538'6" 6&

X X

28 Removed i

29 Drywell Core Spray 1.ine 1404-10','

573' 231*

X X

30 Drywell Cure Spray Line 1403-10" 563' 336*

X X

31 bryuell llPCI Line 2305-10"

$63' 14 &

X X

32 Drywell Target itock Valve 203-3A 542'6" 14*

X X

33 Dryuell Target 1:ock Valve 203-3A 542'2" 31*

X X

34 Dryuell Target liock Valve 203-3A 540' 19*

X X

35 Drywell Target 1(ock Valve 203-3A 540'6" 34*

X X

• Modifications to this table due to changes in high radiation should be submitted to the llRC as part of the next license arne ndme n t request.

Amendment No. 62 DPR-25 91e-2

t DPR-25 H.

Racirculation Pump Flow Hiematch an earthquake or severe transient while allowing normal thermal motion during startup and shutdown.

~

Tha 1.PCI loop selection logic has been described in The consequench of an inoperable snubber is an in-the Dresden Nuclear Power Station Units 2 and 3 crease in the probability of structural den. age to FSAR, Amendments 7 and 8 For some limited low piping as a result of a seismic or other event probability accidents with the recirculation loop initiating dynamic loads.

It is therefore required cperating with large speed differences, it is pos-that all snubbers required to protect the primary sible'for the logic to select the wrong loop for coolant system or any other safety system or com-injection. For these limited conditions, the core ponent be operable during reactor operation.

spray itself is adequate to prevcnt fuel tempera-tures from exceeding allowable limits, llowever, Because the snubber protection is required only to limit the probability even further, a procedural during lou probability events, a period of 72 linitation has been placed on the allowable vari-hours is allowed for repairs or replacements.

In acion in speed between the recirculation pumps.

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 per-Tha licensee's analyses indicate that above 80%

mit an orderly shutdown consistent with standard power the loop select logic could not be expected operating procedures. Since plant startup should to function at a speed differential of 15%. Below not comuence with knouingly defective safety re-20% pouer, the loop select logic would not be ex-lated equipment, Specification 3.6.I.4 prohibits pected to function at a speed differential of 20%.

startup with inoperable snubbers.

This specification provides'a margin of 5% in pump spsed differential before a problem could arise.

When a snubber is found inoperable, a review shall If the reactor is operating on one pump, the loop be performed to determine the snubber node of select logic trips that pump before making the failure. Results of the review shall be used to loop selection.

determine if an engineering evaluation of the safety-related system er component is necessary. The In addition, during the start up of Dresden Unit 2, engineering evaluation shall determine whether or it was found that a flow mismatch between the two not the snubber nude of failure has imparted a signi-sets of jet pumps caused by a difference in re-ficant effect or degradation on the support component circulation loops could set up a vibration until or system.

o niscatch in speed of 27% occurred. The 10% and 15% speed nismatch restrictions provioe additional All safety related hydraulic snubbers are visusily nargin before a pump vibration problem will occur, inspected for overall integrity and operability.

The inspection will include verification of proper ECCS performance during reactor operation with one orientation, adequate hydraulic fluid level and

• recirculation loop out of service has not been proper attachment of snubber to piping and structures.

analyzed. Therefore, sustained reactor operation under such conditions is not permitted.

All safety related mechanical snubbers are visu-ally inspected for overall integrity and opera-1.

Snubbers (Shock Suppressors) bility. The inspection will include verification of proper orientation and attachments to the piping Snubbers are designed to prevent unrestrained pipe and anchor for indications of damage or impaired cotion under dynamic loads as might occur during operability.

99a

• ndment No. )( 62

1 DPR 25 The inspection frequency is based upon maintaining a When the cause of rejection of the snubber is constant level of snubber protectica. Thus, the re-clearly established and remedied for that snubber quired inspection interval varies inver:~Ps wa ti. the and for any other snubbers that may be generically observed snubber failures. The number of inoperaLle susceptible, and verified by inservice functional snubbers found during a required inspection deter-testing, that snubber may be exempted from being mines the time interval for the next required in-counted as inoperable. Cenerically susceptible spection.. inspections performed before that intesval snubbers are those which are of a specific make or has elapsed may be used as a new reference point model and have the same design features directly

.o determine the next inspection, llowever, the resu lts related to rejection of the snubber by visual in-of such early inspections performed before the spection or are similarly located or exposed to original require time interval has elapsed (nominal the same environmental conditions such as tempera-time less 25%) may not be used to lengthen the re-ture, radiation, and vibration.

quired inspection interval. Any inspection whose results require a shorter inspection interval will Honitoring of snubber service life shall consist override the previous schedule, of the existing station record systems, including To further increase the assurance of snubber re-the central filing system, maintenance files, safety-related work packages, and snubber inspection liability, functional tests will be performed once records. The record retention programs employed at each refueling cycle. A representative sample of the station shall allow station personnel to main-10% of the safety-related snubbers wi!! be func-tain snubber integrity. The service life for tionally tested. Observed failures on these samples hydraulic snubbers is 10 years. The hydraulic will requite testing of additional units, snubbers existing locations do not impose undue safety implications on the piping and components be-Ilydraulic snubbers and mechanical snubbers may each cause they are not exposed to excesses in environ-be treated as different entities for the above mental conditions. The service life for mechanical surveillance programs.

enubbers is 40 years, lifetime of the plant.

The mechanical snubbers are installed in areas of harsh Ilydraulic snubber testing will include stroking of environmental conditions because of their dependa-the anubbers to verify piston movement, lock-up, bility-over hydraulic anubbers in these areas. All and bleed. Functional testing of the mechanical snubber installations have been thoroughly engineered snubbers will consist of verification that the providing the necessary safety requirements. Evalua-force that initiates free movement of the snubber tions of all snubber locations and environmental in either tension or compression is less than the conditions justify the above conservative snubber maximum breakaway friction force. The remaining service lives.

portion of the functional test consisting of veri-fication that the activation (restraining action) is achieved within the specified range of accelera-tion in both tension and compression will not be I

done.

This is due to the lack of competitive marketable test fixtures available for station use.

l Therefore, until,such time as test fixtures become available, only part (i) of the test will be per-I formed; part (ii) will not be done.

I

' Amendment No. JM( 62 996

4 f *ar UNITED STATES

,og

+

g'-

g NUCLEAR REGULATORY COMMISSION s.

c WASHINGTON, D. C. 20555 E

O COMMONWEALTH EDIS0N COMoANY

,**..*,o

-AND IOWA-ILLINDIS GAS XRD ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES STATION UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 76 License No. DPR-29 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Commonwealth Edison Company 1

(the licensee) dated April 16, 1981 as supplemented by letters i

dated September 29 and October 21, 1981, complies with the standards i

and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations 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 Commission; C.

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 Commission's regulations; D.

The issuance of this ' amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-29 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.76, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

,w

I

.l

?

f i

i I

i 2-i e

t t

I t

3.

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

i FOR THE NUCLEAR REGULATORY COMMISSION a

i Domenic B. Vassallo, Chief I

Operating Reactors Branch #2 Division of Licensing I

{

Attachment:

Changes to the Technical j

Specifications Date of Issuance: April 28,1982 I

1

\\

1 l

I i

s i

t i

i

?

i i

6 4

f

+

f ATTACHMENT TO LICENSE AMENDMENT N0. 76 i

FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 4

Revise the Appendix "A" Technical Specifications as follows:

Remove Replace I'

3.6/4.6-Sa 3.6/4.6-Sa 3.6/4.6-6 3.6/4.6-6 3.6/4.6-7 3.6/4.6-7 3.6/4.6-13a j

3.6/4.6-14 3.6/4.6-14 3.6/4.6-14a 3.6/4.6-15 3.6/4.6-15 3.6/4.6-15a 3.6/4.6-15a 3.6/4.6-15b

- 3.6/4.6-15b 3.6/4.6-15c 3.6/4.6-15d 3.6/4.6-15e 3.6/4.6-15f 3.6/4.6-15c 3.6/4.6-159 i

QUAD-CITIES DPR-29 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> unless the loop is sooner returned to service.

I.

Shock Suppressors (Snubbers) 1.

Shock Suppressors (Snubbers) 1.

During all modes of operation The following surveillance except Shutdown and Refuel, all requirements apply to all l

snubbers listed in Table 3.6-1 snubbers listed in Table 3.6-1.

shall be operable except as l

noted in 3.6.1.2 following.

1.

Visual inspections shall be performed in accordance with 2.

From and af ter the time that a the following schedule uti-j snubber is determined to be in-lizing the acceptance operable, continued reactor criteria given by Specifica-l operation is permissible during tion 4.6.1.2.

j the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> only if l

the snubber is sooner made Number of Snubbers

{

operable.

Found inoperable Next During inspection Required 2

i 3

If the requirements of 3.6.1.1 or During inspec-Inspection and 3.6.1.2 cannot.be met, an tion interval Interval l-orderly shutdown shall be l-ini tiated and the reactor shall 0

18 months be in a cold shutdown condition 1 25%

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

1 12 months j

4.

If a snubber is determined tc be 1 25%

Inoperable while the reactor is in the Shutdown or Refuel mode, 2

6 months i

the snubber shalI be made 1 25%

operable prior to reactor start-3,4 124 days up.

t 25%

5 Snubbers may be added to safety-related systems without prior 5,6,7 62 days license Amendment to Table 3.6-1 1 25%

provided that a revision to Table i

3 6-1 is included with the next t 8 31 days license amendment request.

1 25%

The required inspection interval shall not be lengthened more than one step at a time.

Snubbers may be categorized in two groups, ' accessible' or ' inacces-sible' based on their accessibility for inspection during reactor l

ope ra t ion. These two groups may be inspected independently according to the above schedule.

Anendment No. g 76 3.6/4.6-Sa

QUAD-CITIES DPR-29 Snubber service life monitoring shall be followed by the snubber surveillance inspection records and maintenance history records.

The above record retention method shall be used to prevent the snubbers from exceeding a service life.

2.

Visual Inspections shall veri fy:

a.

There are no visible indications of damage or impai red opera-bility, and b.

Attachments to the foundation or supporting structure are secure.

c.

For hydraulic snubbers, the hydraulic fluid reservoir and fluid connections shall be inspected for ope rabi l i ty.

3 Once each refueling cycle a representative sample of 10%

of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.

For each snubber that does not meet the functional test criteria, an additional 10% of that type of snubber shall be functionally tested.

4.

The hydraulic snubber shall be functionally tested for operability, including verification of proper piston movement, lockup, and 1

bleed. When competitive marketable test fixtures are available, but no later than 12/31/83, the functional test shall include demonstrating snubber bleed, or release, ratel is within the specified range in compression or tension.

5.

The mechanical snubber functional tests shall verify:

a.

That the breakaway force knendment No. 76 that initiates free move-3.6/4.6-6 ment of the snubber rod

QUAD-CITIES DPR-29 in either tension or compression is less than the specified maximum force.

b.

That the activation (re-straining action) is achieved within the specified range of acceleration in both tension and compression. This test cannot be performed until competitive marketable test fixtures are manufactured and on site. Until such rest fixtures are available, but no later than 12/31/83, the functional test for mechanical snubbers will be limited to 4.6.1.5.a.

6.

When a snubber is deemed inoperable, a review shall be conducted to determine the mode of failure and to decide if an engineering evaluation should be performed.

If the engineering evaluation is deemed necessary, it will deter-mine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.

7 If any snubber selected for functional testing either fails to lockup or fails to move, i.e.,

frozen in place, the cause will be evaluated and if determined to be generically deficient all snubbers of the same design, subject to the same defect shall be functionally tested.

8.

In addition to the regular sample, snubbers whicl, failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be in-cluded for the resampling Amendment No. 76

~

t QUAD-CITIES OPR-29 I

i l.

SiluBBERS All snubbers are required OPERABLE to ensure that the structural integ ri ty 1

of the reactor coolant system and all other safety-related systems is main-tained during and following a seismic or other event initiating dynamic loads.

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 ef fect 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 number of inoperable snubbers found during an inspection.

Inspections per-formed before that interval has elapsed may be used as a new reference point to determine tha 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.

Snubber service life monitoring will be followed by the existing snubber surveillance inspection records and maintenance history records.

The above record retention method should be used to prevent the hydraulic snubber from exceeding a service life of 10 years and the mechanical snubbers from exceeding a service life of 40 years.

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, and verified by inservice functional testing, that snubber may be exempted f rom being counted as inoperable. Generically susceptible 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 conditions such as temperature, radiation, and vibration.

To provide assurance of snubber functional reliabili ty, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at refueling cycle intervals.

Hydraulic snubber functional testing i

I will include stroking of the snubbers to verify' piston movenent, lockup and bleed.

Functional testing of the mechanical snubber will consist of verifi-cation that the force that initiates free movement of the snubber in either tension or compression is less than the maximum breakaway friction fo rce.

The remaining portions of the functional test consisting of verification that the activation (restraining action) is achieved within the specified range of acceleration in both tension and compression will not be done. This is due to the lack of competitive marketable test equipment available for Station use.

Amendment No. )f 76 3 6/4.6-14

QUAD-CITIES DPR-29 When a snubber is found inoperable, a review shall be performed to determine the snubber mode of failure.

Resul ts of the review shall be used to determine i f an engineering evaluation of the safety-related system or component is necessary. The engineering evaluation shall determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the support component or system.

Observed failures of these sample snubbers shall require functional testing of additional units.

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

Amendment No. 76 3.6/4.6-14a

quRD-CITIES DPR-29 Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)

Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Snubber Elevation Radiation Area Difficult During Normal During Normal Type

• Number Location (feet)

During Shutdown to Remove Operation Operation M

l-1 Drywell; core spray return 644 l

X X

line 1-1403-10" X

X.

M l-2 Drywell; core spray ' return 644 line 1-1403-10" M

l-3 Drywell; core spray return 642.

X X

line 1-1404-10" M

1-4 Drywell; core spray return 642 X

X line 1-1404-10" M

l-5 Drywell; RHR return line 603 X

X l-1012A-16" M

l-6 Drywell; RHR return line 599 X

X l-1012A-16" M

1-7 Drywell; RHR return line 593 X

X l-1012B-16" i

M l-8 Drywell; RHR return line

_603 X

X l-1012B-16" M

l-9 Dry.. ell; RHR shutdown 601 X

X cooling supply line 1-1025-20"

• M = Mechanical Snubber H = Hydraulic Snubber

' Amendment No. ;M( 76 3.6/4.6-15

QUAD-CITIES 1

DPR-29 Table 3.6-1 SAFETY RELATED SHOOK SUPPRESSORS (SNUBBERS)

Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Snubber Elevation Radiation Area Difficult During Normal During Normal Type

• Number Location (fect)

During Shutdown to Remove Operation Operation M.

1-10 Drywell; RHR shutdown 601 I

X X

cooling supply line l-1025-20" M

l-11 Drywell; "A" recirculation 586 at 135 X

X X

purp to shield wall M

1-12 Drywell; "B" recirculation 586 at 315 X

x x

pump to shield wall N

1-13 Drywell; "A" reci rculation 586 at 146.5 X

X X

pump to support M

l-14 Drywell; "B" recirculation 586 at 304 X.

X X

pu p to support M

l-15 Drywell; "B"

recirculation 586 at 326.5 X

x x

pu.p to support M

l-16 Drywell; recirculation ring 610 at 900 X

X X.

header X

l M

l-17 Drywell; recirculation ring 610 at 2700 x

X header M

l-18 Drywell; "A"

recirculation 612 at 135o X

X X

pu p motor to support eM = Mechanical Snubber

]

H = Hydraulic Snubber Amendment No.,3r' 76 3.6/4.6-15a

u, QUAD-CITIES DPR-29 Table 3.6-1 1

SAFETY RELATED SHOOK SUPPRESS 0RS' (SNUBBERS)

' Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Snubber Elevation Radiation Area Difficult N During Normal Du' ring Normal Typc* Number Location (feet)

During Shutdown to Remove Operation Operation M

l-19 Drywell; "B" racirculation 612.at 3150 i

X A'

X pump motor to support M

l-20 Drywell:

ecirculation ring 612 at 1950 X

X X

header o <upport ecirculation 588 at 1240 X

X X

M l-21 Dry. ell punp tr

.:: o '

M l-22 Dryacil; "A" r circulation 602 at 1220 X

X pur.p r.otor to shield wall M

l-23 Dryael l ; "A" reci rculation 602 at 1480 X

X

. pump cotor to shield wall M

1-24 Dryv.el l ;

"B" reci rcula tion 602 at 302 X

X purp r.otor to shield wal1 M

l-25 Drysell; "B"

recirculation 602 at 3280 X

X purp -otor to shield wall M

l-26 Dryt.cIl; rain stream 619 X

X X

relief valve 1-203-3A M

l-27 Dry <.-ell; main stream 619 x

x X

relief valve 1-203-3A AM = Mechanical Snubber H = Hydraulic Snubber Amendment No. )M( 76 3.6/4.6-15b

QUAD-CITIES DPR-29 Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)

Snubbers Snubbers Snubbers Snubber,in High Especially inaccessible Accessibl'e Snubber.

Elevation Radiation Area

' Difficult During Normal During Normal Type

• Nur.ber Locatlon (feet)

During Shutdown to Remove Operation Operation M

t-28.

Drywell; main stream 619 i

X X

relief valve 1-203-3A-M 1-29 Dryuell; main stream 619 X

X X

relief valve 1-203-3A M

'l-30 Dryuell; northeast end of 605 X

X CRD cluster M

1-31 Drywell; northwest end of 605 X

X 1

CRD cluster M

l-32 Drywell; southeast end of 605 X

X 2

CRD cluster

(

M l-33 Dryuell; southwest end of 605 X

X CR0 cluster I

t OM = Mechanical Snubber H = Hydraulic Snubber Amendment No. 7t3 3.6/4.6-15c

~ _. _.. _ _ _ -. - _.

QUAD-CITIES

~

DPR-29 Tabic 3 6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)

Snubbers Snubbers Snubbers Snubber..in High Especially inaccessible Accessible Elevation Radiation Area Difficult During Normal During Normal Typc* Humber Location (feet)

During' Shutdown to Remove Operation Operation Snubber I

X H

1-36 Reactor bldg; RHR shutdown 590 cooling supply line 1-1025-20" X

X H

1-37 Reactor bldg; RHR shutdown 573 cooling supply line 1-1024A-20" a

X X

H 1-38 Reactc-bldg; RHR shutdown 573 cooling supply line 1-1024A-20" X

X H

1-39 Reactor oldg; RHR shutdown 573 cooling supply line 1 - 1024 A-20" X

X 573 H

1-40 Reactor bldg; RHR shutdown cooling supp!y line 1-1024A-20" X

H 1-41 Reactor bldg; RHR pump 562 X

supply line 1-1015A-24" X

H 1-42 Reactor bldg; RHR pump 562

.X supply line 1-1015-24" 610 X

X X

M l-43 Dry. sell; Recirc line l-201-22"

• M = Mechanical Snubber H = Hydraulic Snubber 3.6/4.6-15d Amendment No. 76

QUAD-CtTICS DPR-29 Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)

Snubbers Snubbers Snubbers Snubber _in High Especially inaccessible Accessible

Snubber Elevation-Radiation Area Difficult During Normal During Normal Type

• Number Location (feet)

During Shutdown to Remove Operation Operation i

M 1-44 Dryveell; Reci rc line 614 X

X X

l-201C-12" M

l-45 Drywell; Recirc line 614 X

X X

1-20lM-12" M

l-46 Drywell; Recirc line 613 X

X X

l-2010-28" M

l-47 Dryt. ell; Recirc line 613 X

X X

l-201C-12" M

1-48 Dry.. ell; Reci rc line 594 X.

X X

1-202A-28" M

l-49 OryceII; RHRS line 627 X

X X

l-1011-k" M

l-50' MStv Rm; Main Steam 615 X

X X-line 1-3001A-24" M

1-51 MStV Rr; 'iain Steam

-615 X

X X

line 1-3001A-24"

• M = Mechanical Snubber H = Hydraulic Snubber Amendment No. 76 3.6/4.6-15e

___.__.._m__.

QUAD-CITIES DPR-29 Table 3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS)

Snubbers Snubbers Snubbers Snubber-in High Especially inaccessible Accessible Snubber Elevation Radiation Area Difficult During Normal-During Normal Type

• Number location (feet)

During Shutdown to Remove Operation Operation M

1-52 MSIV Rm; Main Steam 615 i

X X

X line 1-3001B-24" i

M l-53 MSIV Rm; Main Steam

-615-X X

X line 1-3001B-24" M

l-54 MSIV Rm; Main Steam 615 X

X X

line 1-3001C-24" h

1-55 MSIV Rm; Main Steam 615 X

X X-line 1-3001C-24" M

1-56 MStV am; Main Steam 615 x

X X

line I-30010-24" M

1-57 MSIV Rm;. Main Steam 615 X

X X

line 1-30010-24" l

i cM = Mechanical Snubber H = Hydraulic Snubber 1

3 6/4.6-15f Amendment No. 76~

Minimum Tcmpecture Requiremer.t per Appendix G of 10 CFP 50 1200 g

f 1100 p

CURVE A (INSERVICE PRESSURE TESTS-s:

f SECTION XI) 1000

/

I I

I

/

/

CURVE B (HE ATUP - COOLDOWN) g g

900 f

[

[

CURVE C (CRITIC AL CORE OPER ATION)

O 800 j

/

G-

/

f 700 y

e 11 E

ll g

600 3

H g

500 jj 0

[

ll MINIMUM BOLTING TEMPERATURE = 100 F 0F 400 MINIMUM OPER ATING TEMPER ATURE = 149 b

H RTNDT = 40 F b

II K = PER SECTION G-2110 OF APPENDIX G 300 i

c'

[

OF THE SUMMER 1973 ADDENDA TO q

SECTION lli OF THE ASME CODE 200 100 0 -1 100 200 300 TEMPERATURE (OF)

Amendment No. [ 76

3. 6/ 4. 6-1 59 l

pa af og c9 o

UNITED STATES

!\\

,o NUCLEAR REGULATORY COMMISSION h,

WASHINGTON, D. C. 20555 i

\\,*****/

COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES STATION UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.70 License No. DPR-30 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by the Commonwealth Edison Company (the licensee) dated April 16, 1981 as supplemented by letter dated September 29, 1981 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations 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 Commission; C.

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 Commission's regulations; D.

The issuance of this amendment will not be' inimical to the common defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility License No. DPR-30 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 70, are hereby incorporated in the 1icense.

The 1icensee shal1 operate the facility in accordance with the Technical Specifications.

ii 2-I, :.

3.

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

~

FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

- Changes to the Technical Specifications Date of Issuance: April 28,1982 1

(

I l

a i-

i ATTACHMENT TO LICENSE AMENDMENT N0. 70 FACILITY OPERATING LICENSE NO. OPR-30 DOCKET N0. 50-265 Revise the Appendix "A" Technical Specifications as follows:

Remove Replace.

3.6/4.6-Sa 3.6/4.6-Sa 3.6/4.6-6 3.6/4.6-6 3.6/4.6-7 3.6/4.6-7 3.6/4.6-13a 3.6/4.6-14 3.6/4.6-14 3.6/4.6-14a 3.6/4.6-15 3.6/4.6-15 3.6/4.6-15a 3.6/4.6-15a 3.6/4.6-15b 3.6/4.6-15b 3.6/4.6-15c 3.6/4.6-15d 3.6/4.6-15c

3. 6/4. 6-15e 3

[

\\

l 1

l i

A

---,.,v

.. -a

, +, -, -,

a7.

a

QlliiD-C i T 1 L S Drn-30 sooner returned to service.

1.

Shock Suppressors (Snubbers) l.

Shock Suppressors (Snubbers)

The following surveillance 1.

During all modes of operation requirements apply to all l

Shutdown and Refuel, all snubbers listed in Table 3.6-1.

except snubbers listed in Table 3.6-1 1.

Visual inspections shall be shall be operable except as l

noted i n 3.6. l. 2 fol icr.iing.

performed in accordance with the following schedule uti-2.

From and after the time that a lizing the acceptance snubber is determined to be in-criteria given by Specifica-operable, cont,N ed reactor tion 4.6.l.2.

operation is permissibic during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> only if flumber of Snubbers the snubber is sooner made Found inoperable flext operabic.

During inspection Required or During Inspec-Inspection If the requirements of 3.6.1.1 Interval 3

tion Interval and 3.6.l.2 cannot be met, an orderly shutdown shall be 18.non ths 0

initiated and the reactor shall i 25%

be in a cold shutdown condition 12 months within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

I 1 25%

4.

If a snubber is determined to be inoperable while the reactor is 6 months 2

in the Shutdown or Refuci mode, i 25%

the snubber shall be made operable prior to reactor start-3,4 124 days up.

i 25%

5 Snubbers may be added to safety-5,6,7 62 days related systems without prior 1 25%

license Amendment to Table 3.6-1 provided that a revision to Tabic

>8 31 days 3.6-1 is included with the next 1 25%

license amendment request.

The required inspection interval shall not be lengthened more than one step at a time.

Snubbers may be categorized in two

' accessible' or 'inacces-

groups, sible' based on their accessibiIity for inspection during reactor operatlon.

These two groups may be inspected independently actoiding to the abnve schedule wu

QUAD-CITIES DPR-30 Snubber service li fe moni toring shall be followed by the snubber surveillance inspection' records and maintenance history records.

The above record retention method shall be used to prevent the snubbers from exceeding a service life.

2.

Visual-Inspections shall veri fy:

a.

There are no visible lt indications of -damage or impai red opera-bility, and

~

i i-'

b..

Attachments to the foundation or supporting structure are secure.

I I

c.

For hydraulic snubbers, the hydraulic fluid 4

I reservoi r and fluid conner.tions shall be inspected for operability.

i 3

Once each refueling cycle a representative sample of lot of the total of each type of snubber in use in the plant shall be functionally-tested ~

either in place or in a bench test.

For each snubber that does not meet the functional

. test cri teria, an. addi tional j

100 of that type of. snubber '

l.

shall be functionally tested.

4.

The hydraulic snubber shall be functionally tested - for ope rabi l i ty, including 4

verification of proper i

piston raovement, lockup, and bleed.

I 5.

The mechanical snubber functional tests shall varify:

~

a.

That the breakaway force that initiates' free move-I ment of the snubber rod i

4

! Amendment No. g 70 3.6/4.6-6 1,

.~. - -,.

QUAD-CITIES DPR-30 Snubber service life monitoring shall be followed by the snubber surveillance inspection records and maintenance history records.

The above record retention method shall be used to prevent the snubbers from exceeding a service life.

2.

Visual Inspections shall verify:

a.

There are no visible indications of damage or impaired opera-bility, and b.

Attachments to the foundation or supporting structure are secure.

c.

For hydraulic snubbers, the hydrau!!c fluid reservoir and fluid connections shall be inspected for operability.

3 Once each refueling cycle a representative sample of 10%

of the total of each type of snubber in use in the plant shall be functionally tested either in place or in a bench test.

For each snubber that does not meet the functional test criteria, an additional 10% of that type of snubber shall be functionally tested.

4.

The hydraulic snubber shall be functionally tested for ope rabi l i ty, including verification of proper piston movement, lockup, and bleed. When competitive marketable test fixtures are available, but no later than 12/31/83, the functional test shall include demonstrating l

snubber bleed, or release, ratel is within the specified range in compression or tension. -

5.

The mechanical snubber functional tests shall verify:

a.

That the breakaway force Amendnent No. 70 that initiates free move-3.6/4.6-6 ment of the snubber rod

~

5 QUAD-CITIES DPR-30 in either tension or compression is less than the specified maximum force.

4 b.

That the activation (re-i straining action) is achieved within the specified range of l

accelerat;on in both terssion and compression. This test cannot be performed until competitive marketable test fixtures are manufactured and on site. Until such rest fixtures are available, but no later than 12/31/83, the functional test for mechanical snubbers will be limited to 4.6.1.5.a.

6.

When a snubber is deemed inoperable, a review shall be conducted to determine the mode of failure and to decide if an engineering evaluation should be performed.

If the engineering evaluation is deemed necessary, it will deter-mine whether or not the snubber mode of failure has imparted a significant ef fect or degradation on the supported component or system.

7 If any snubber selected for fu~nctional testing either fails to lockup or fails to move, i.e.,

frozen in place, the cause will be evaluated and if determined to be generically deficient all snubbers of the same design, subject to the same defect shall be functionally tested.

8.

In addition to the regular sample, snubbers which failed the previous functional test shall be retested during the next test period.

If a spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another position) and the spare snubber shall be retested. Test results of these snubbers may not be in-cluded for the resampling Amendment No.

70 3.6/4.6-7

QUAD-CITIES DPR-30 1.

S!!UBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is main-ained during and following a seismic or other event initiating dynamic loads.

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 ef fect 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 number of inoperable snubbers found during an inspection.

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

However, the resul ts 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.

Snubber service life monitoring will be followed by the existing snubber surveillance inspection records and maintenance history records.

The above record retention method should be used to prevent the hydraulic snubber from exceeding a service li fe of 10 years and the mechanical snubbers from exceeding a service li fe of 40 years.

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, and veri fied by inservice functional testing, that snubber may be exempted f rom being counted as inoperable.

Generically susceptible snubbers are those which are of a speci fic 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 envi ronmental condi tions such as temperature, radiation, and vibration.

To provide assurance of snubber functional reliabili ty, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at refueling cycle intervals.

Hydraulic snubber functional testing will include stroking of the snubbers to verify piston movement, lockup and bleed.

Functional testing of the mechanical snubber uill consist of veri f t-cation that the force that ini tiates f ree movement of the snubber in either tension or compression is less than the maximum breakaway f riction force.

The remaining portions of the functional test consisting of verification that the activation (restraining action) is achieved wi thin the speci fied range of acceleration in both tension and compression will not be done.

This is due to

he lack of competi tive marketable test equipment available for Station use.

Amendment No.JFr 70 3.6/4.6-14

'a liC'fE' m

y m_

m.

QUAD-CITIES DPR-30 When a snubber is found inoperable, a review shall be performed to determine the snubber mode of failure.

Results of the review shall be used to determine if an engineering evaluation of the safety-related system or component is necessary. The engineering evaluation shall determine ~ whether or not the snubber mode of failure has imparted a signi ficant ef fect or -

degradation on the support component or system.

Observed failures of these sample snubbers shall require functional testing of additional units.

Hydraulic snubbers and mechanical snubbers may each be treated as a di f ferent enti ty for the above surveillance programs.

s 3.6/4.6-14a Amandment No. 70

QUAD-CITIES DPR-30 Tabic 3.6-1 SAFETY RELATED SHOCK-SUPPRESSORS (SNUB 8ERS)

Snubbers Snubbers Snubbers Snubber in High Especially inaccessible.

Accessible l

Snubber Elevation Radiation Area.

Difficult During Normal

-During Normal Type

• Number Location (feet)

During Shutdown to Remove Operation

~0peration M

2-1 Drywell; core spray return 644 X

X line 2-1403-10" M

'2-2 Drywell; core spray return 644 X

X line 2-1403-10" M

2-3 Drywell; core spray return 642' X

X line 2-1404-10" M

2-4 Drywell; co're spray return 642 X

X line 2-1404-10" M

2-5 Drywell; RHR return line 603 X

X 2-1012A-16" M

2-6 Drywell; RHR return line 599 X

X 2-1012A-16" M

2-7 Drywell;-RHR-return line.

598 X

X 2-1012B-16" N 8 Drywell; RHR. return line.

603 X

X 2-1012B-16" M

2-9 Drywell; RHR shutdown 601 X

X cooling supply line 2-1025-20"

• M = Mechanical Snubber H = Hydraulic Snubber Amendment No.,2f 70 3.6/4.6 15

i OUAD-CITICS UPn-30 j

Table 3.6-1 I

SAFETY RELATED SHOCK SUPPRESSORS (SNUBBERS) i Snubbers Snubbers Snubbers Snubber in High Especially inaccessible.

Accessible-I Snubber Elevation Radiation Area Difficult During Normal During Normal-i Tyce* Number Location (feet)

During Shutdown to Remove Operation Operation 4

[

M 2-10 Drywell; RHR shutdown 601 i

X X

cooling supply line 1

2-1025-20" M

2-11 Dryweil; "A"

recirculation 586 at 135

.X X

'X pump to shield wall i

M 2-12 Drywell; "B" reci rculation

.586 at 315 X

X X

purp to shield wall 2-13 Drywell; "A"

recirculation

.586 at 146.50 X

X X

pump to support l

M 2-14 Drywell; "B" recirculation 586 at 326.5 X

X

~X pump to support M

2-15 Drywell; "B" reci rcula tion 586 at 304 X

X X

purp to support 4

0 X

X X

M 2-16 Drywell;Jrecirculation ring 610 at'90 header i

M 2-17 Drywell; recirculation ring 610 at 270

.X X

X 0

header 1

i M

2-18 Dryv. ell; "A" reci rculation 612 at 135 X

X X

pu p motor.to support i

^M = Mechanical Snubber

}

H = Hydraulic Snubber I

[ : Amendment No. 3Y' 70 3.6/4.6-15a

QUAD-CITIES' DPR-30 Table.3.6-1 SAFETY RELATED SHOCK SUPPRESSORS (SNU33ERS)

Snubbers Snubbers Snubbers Snubber.in High Esoccially inaccessible Accessible 5 ;nber Elevation Radiation Area Difficult During Normal During Nornal.

Ty:e*

.. :er Location (feet)

During Shutdown tc Remove Operation Operation 2

Drywell; "B" recirculatica 612 at 3150 i

X X

X pump motor to support M

2-2:

Drywell; recirculation ri :

612 at 195o X

X X

header to support e

.2-Zi Drywell; "A" reci rculatic.

538 at 1240 X

X

.X pump to support M.

Dry. sell; "A"

recirculation 602 lat 1220 X

X

~ ~~

pump motor to shie'id wal' 2-23

.Drywell; "A"

recirculati:-

602 at 1480 X

X pump r.otor to shield wali 2 ~-

Drywell; "B" recirculatie-602 at 3020 X

X pump motor to shield wall 2~~

Drywell ; "B" reci rculatie-602 at 3280 X

X pump rotor to shield..a

2 ~5 Drywel l ; ma in st resa

-619 X

X X

relief valve 2-203-3A 2~~

D rywell ; main s t rean 619 X

X

.X relief valve 2-203-3A de: anical Snubber

• • =

.:-culic Snubber

- =

Ameni ent No. E 70 3 6/4.6-15b

CUAD-CITIES DPR-30 Table 3.6-1 SAFE".'/ RELATED SHUCK SUPPRESSORS (SNUBBERS)

Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible Snubber Elevation Radiation Area Difficult During Mormal During Normal Type

• Number Location (feet)

During Shutdewn to Fcmove Operation 0:eration M

2-23 Drywell; main stream 619 i

X X

x relief valve 2-203-3A M

2-29 Drywell; main stream 619 X

X X

relief valve 2-203-3A M

2-3D Dry.; ell; northeast end of 605 X

X CRD cluster M

2-31 Drywell; northwest end of 605 X

X CRD cluster M

2-32 Dry.. ell; southeast end of 605 X

X CRD cluster M

2-33 Dryucil; southwest end of 605 x

x CRD cluster H

2-34 Reactor bldg; RHR Pump D 558 X

X supply line 2-10160-14" H

2-35 Reactor bldg; RHR Pump D 558 X

X supply line 2-1016D-14" H

2-36 Reactor bldg; RHR shutdown 591 X

X cooling supply lin.

2-1025-20"

• M = Mechanical Snubber H = Mydraulic Snubber Amendment No. 70 3.6/4.6-15c

QUAD-CITIES OPR-30 g

l Table 3.6,

SAFETY RELATED SHOCK SUPPRESSORS { SNUBBERS)

Snubbers Snubbers Snubbers Snubber in High Especially inaccessible Accessible-Snubber Elevation Radiation Area Difficult During Normal During Norral Tvoe* Number Location (feet)

During Shutdown to Remove

' Operation Ooeration H

2-37 Reactor bldg; HPCI steam 588 j

X X-supply line 2-2305-10" X

H 2-38 Reactor b1dg; Pressure 646 Suppression vent line 2-1603-18" X

H 2-39 Reactor bldg; SB3TS 655 i

vent line 2-1607-6" X

H 2-LO Reactor b1dg; SSGTS 655 vent line 2-1607-6" X

H 2-41 liSlV Rm; RCIC stean 605 X

line 2-1307-3" X

H 2-42 MSIV Rn;.RCIC steam 605 X

line 2-1307-3" 1

• M = Mechanical Snubber H.= Hydraulic Snubber i

j Amendment No. 70 3.6/4.6-15d

o Minimum Temperature Repirements per Appendiv G of *C CFR 50 1200 f

1100

/

--CURVE A (INSERVICE PRESSURE TESTS-f SECTION XI)

I 1000

/

I I

I l

r

/

CURVE B (HtE ATUP - COOLDOWN) g l

$8 i

I

[

[

-CURVE C (CRITICAL CORE OPE R ATION)

+--

O 800 f

I Q-

/

700 e

i 600 I

ea

$5 i

[

l MINIMUM BOLTING TEMPERATURE = 100 0F 9

0F l

MINIMUM OPER ATING TEMPERATURE = 149 400 l

RTNDT = 40 F 0

y b

K = PER SECTION G 2110 OF APPENDIX G 300 l

g j

g

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OF THE SUMMER 1973 ADDENDA TO E

SECT!ON 111 OF THE ASME CODE g

200

. 8 -_

I I _

l

.. _ l.

_.I

. I _. _.

i

r. -

oo 100 200' 300 TEMPERATURE (0 -)

1 Amendment No.

F, 70 3.6/4.6-15e

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