ML20010A682

Tech Spec Re Special Test Exceptions Coolant Circulation, Refueling Operations Shutdown Cooling & Coolant Circulation & Control Room Emergency Ventilation Sys

ML20010A682
Person / Time
Site:	Calvert Cliffs
Issue date:	07/30/1981
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20010A680	List: ML20010A679 ML20010A682
References
NUDOCS 8108120026
Download: ML20010A682 (7)

Text

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SPECIAL TEST EXCEPTIONS COOLANT CIRCULATION LIMITING CONDITION FOR OPERATION 3.10.5 The reactor coolant circulation requirements of Specification 3.4.1

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may be suspended and all reactor coolant pumps and shutdown cooling pumps may be de-energized during the time intervals required 1) for local leak rate testing of centainment penetration number 41 pursuant to the require-ments of Specification 4.6.1.2.d and 2) to permit maintenance on valves located in the common shutdown cooling suction line or on the shutdown cooling flow control valve (CV-306) provided:

a. No operations are permitted which could cause dilution of the reactor oolagt system ron conc trat, ion G C Nf.

~C&q % PJy are de-s+gt ,d f&wd Specit cAllpartgjead,

b. The xenon reactivity is < 0.1% ak/k and is approaching stability, and

c. The SHUTDOWN MARGIN requirement of Specification 3.1.1.2 is verified at least ance per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when no shutdown cooling or reactor coolant pumps are in operation.

APPLICABILITY: MODES 4 and 5.

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ACTION: ,

With the requirements of the above specification not satisfied, suspend -

all operations involving local leak rate testing of containment penetration l number 41, maintenance on valves located in the comon shutdown cooling .

suction line, and maintenance on valve CV .306.

• SURVEILLANCE REOUIREMENTS 4.10.5.1 TFa charging pumps shall be verified de-energized and the charg-ing flow paths shall be verified closed at least once per hour.

4.10.5.2 The xenon reactivity shall be determined to be < 0.1% Ak/k and approaching stability within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> prior to suspending reactor coolant circulation.

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SHUTDCWN COOLING AND COOLANT CIRCULATION e LIMITING CONDIT!0'i FCR OPERATION 3.9.8.1 At least one shut:cwn cooling loop shall be in operation.N APPLICABILITY:, M00E _6 atgil _reac;or water level s.

ACTION: _

a. With less than One squtdown cooling loop in operation suspend all operations involving an increase in the reactor decay heat l load or a . aduc tien ir, boron concentration of the Reactor Coolant Systemn Close all containment penetrations providing ll cirect access from the containment atmosphere to the outside atmosphere within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The shutdown cooling pumps may be de-energized during the time intervals required for local leak

' , rate testing of containment penetration number 41 pursuant to the requirements of Specification 4.6.1.2.d and/or to pe mit maintenance on valves located in the corr.on shutdown cooling iY / suction _line, provided (1) no operations are permitted which hio pu </K ou.c cause Oilution of the reactor coolant system Doron g, yd concentration (2) alt CORE ALTERATIONS are suspended. (3) all

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g containment penetrations providing direct access from the i

gg containment atmosphere to the outside atmosphere are maintained closed, and (c) the water level above the top of the irradiated fuel is greater than 23 feet

b. The provisions cf Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENT' __

4.9.8.1 A shutdown cooling loop snall be determined tc be in operation and '

circulating reactor coolant at a flow rate of > 3000 gpm" at least once per t 4. hours.

• The shutdown cooling loop may be removed from operation for up to I hoJr per

! 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> peri 0d curing the cerformance of CORE ALTERATIONS in the vicinity of the reactor pressure vessel hot legs.

"> 1500 gpm when :ne Reactor Coolant System is drained to a level below the misplane of the hot leg.

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PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY '.'rNTILATION SYSTEM LIMITING CONDITION FOR OPERATION J

3 7.6.1 The control room emergency ventilation syster: shall be OPERABLE with

a. Two filter trains,

b. Tvo air conditioning units,

c. Two isolation valves in each control room outside air intake duct, CDM%

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d. Two isolation valves in the duct, and Y$se may CO

e. One isolation valve in the toWL -

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c. With one isolation valve per control room outside air intake duct inoperable, operatich may continue provided the other isolation valve in the same duct is maintained closed; otherwise, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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d. With one c c t c. rc: cxha :t duct isolation valve inoparable.

restore the ir. operable valve to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

e. With the toilet area exhaust duct isolation valve inoperable, restore the inoperable valve to OPERABLE status within 24 hot.rs or be in at lea',t HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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, 0Coffulo$ lit 4h PIRIT SYS7DtS 3/4.7.8 S?1UBBERS L!?4ITING CGIDITIOJ FOR OPERATIGI 3.7.8.1 All snubbers listed in Table 3.7-4 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4. (MODES 5 and 6 for snubbers located on systems required OPERABLE in those MODES).

ACTIG3: With one or more snubbers inoperable, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace or restore the inoperable stubber(s) to OPERABLE status or declare the supported system inoperable and follw the appropriate ACTIO1 statenent for that systen.

SURVEILLANCE REQUIRENENTS ___

4.7.8.1 Each snubber shall be denonstrated OPERABLE by perfomance of the following augrnented inservice inspection program and the regairenents of Specification 4.0.5.

a. Visual Insoection Visual inspections shall be performed in accordance with the following schedule:

Inoperable snubbers Subsequent Visual *#

per Insnection Period Insoection Period 0 18 months 1 25%

1 12 months 3 25%

2 6 months 1 25%

3, 4 124 days 1 25%

5,6,7 62 days 25%

8 or more 3.'. days 1 25%

The snubbers may be categorized into two groups: Those accessible and those inaccessible during reactor operation. Each group may be inspected independently in c.Lcordance wi+,h the above schedule.

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

1. 1he provisions of Specification 4.0.2 are not applicable.

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b. Visual Inspection Acceptance Criteria Visual inspections shall verify that there are no visible indications of damage or impaired OPERABILITY, and shall inc]ude but am not necessarily limited to, inspection of the hydraulic fluid reservoirs, fluid connections, and linkage connections to the piping and anchors. Snubbers which appear inoperable as a result of visual inspections may be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and/or (2) the affected snubber is functionally tested in the as found condition and detentined OPERABLE per Specificaticm 4.'Z8.1.d, as applicable.

c. Fumtional Tests A representative sample of 100 of the snubbers in use in the plant shall be functionally tested either in place or in a bench test once per 18 months during shutdown. For each snubber which does not meet the func-tional test acceptance criteria of Specification 4.7,8.lsi, an additioral 5% of the snubbers shall be functionally tested until no more failures are found or all snubbers have been functicnally tested.

Snubbers idencified in Table 3.7-4 as "Especially Difficult to Renove" or in "High Exposure Zones"(During Shutdowr$ shall also be included in the  :

representative sample.*

In addition to the regular sample, srr bbers 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 stubber, then both the failed snubber (if it is repairal and installed in another position) and the spare snubber shall be retested during the next test period.

Test results of these snubbers shall not result in additional functional testing due to failure.

l If any snubber selected for functional testing either fails to lockup or fails to trove, i.e. , frozen in place, the cause will be evaluated for

! further action or testing.

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• Permanent or other exetptions frcm functional testing far individual snubbers in l

these categories may be granted by the Ccrrmission only if a justifiable basis for j exe:ption is presented and/or sr.abber life destructive testing was performed to qualify snubber operability for all design conditions at either the ccrnpletion of their fabrication or at a subsequent date.

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d. Hydraulic Snubbers Functional Test Acceptance Criteria The hydraulic snubber functional test shall verify that:

1. Activation (restraining action) is achieved within the specifhd range of velocity or acceleration in both tension and ccepression.

2. Snubber bleed, or rtelease rate, where required, is within the speci-fled range in ccrnpression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacenent shall be verified.

e. Snubber Service Life Monitorina A record of the service life of each snubber, the date at which the designated service life ccrinences and the installation and maintenarce records on which the designated service life is based shall be main-tained as required by Specification 6.lO.2.tn.

At least once per 18 months + 25%, the installation and maintenance records for each snubber listed in Table 3.7-4 shall be reviewed to verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life re-view. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life

' hall be reevaluated or the snubber shall be replaced or reconditioned so as to exterd its service life beyond the date of the rc.ct scheduled service life review. This reevaluation, replacanent or reconditioning shall be irdicated in the recortis.

f. Snubbers served by a common hydraulic reservoir are indicated by a bracket in Table 3 7-4 All reservoirs serving more than one snumber shall be inspected to ensure adequate hydraulic level :

1. Wi * .hin 7 days after reactor tartup^ following a major outage er following any maintenance in the immediate vicinity of these snubbers, reservoirt or associated hydraulic piping; and

2. Every 31 days ; 25 percent.

CALVERT CLIFFS - UNIT 14 VMIT 2 3/4 7-26a

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PP yy SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE OR lilGil EXi mt HE ESPECIALLY DIFFICULT d- f. NO. 0!i, LOCATION AND ELEVATION INACCESSIBLE ZOf1E** TO REMOVE 55

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• Snubbers may be added tohsafety related sys,temshwithout prior License Amendment to Table 3.7-4

@ prnvided that a revision to Table 3.7-4 is included with the next License Amendment request.

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• • Modifications to this column due to changes in high radiation areas may be made without prior License Amendment provided that a revision to Table 3.7-4 is included with the next License

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'D5 *** Smthers serval by c coanon hydraulic reservoir are irxiicated by a bracket.

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A 0 6 9 cS(FCLtt-44) ptAtrT SYSTU G BASES environment. The operation of this systen ard th i resultant effect on offsite dosage calculations was assumed in the accident analyses.

3/4.7.3 SNUBBERS All srubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads. Srobbers excluded frun this inspection progran are those installed on non-safety related systems and then only if their failure or failure of the systen on which they are installed, 4

would have no adverse effect on any safety related systen.

i The visual inspection frequency is based upon maintaining a constant level of snubber protection to systens. Therefore, the reqaired inspection interval varies inversely with observed srubber failures and is de*cnnined by the rnJnber of inop-erable srubbers found during an inspection. Inspections perfonned befort that inter-val has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early ir.'>ections perfonned before the original required time interval has elapsed (raninal time less 25%) may not be used to lerxf&en the re-quired inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

When the cause of the rejection of a stubber is clearly established and remedied for that stubber and for any other srubbers that may be generically susceptible, and verified by inservice functional testing, that stubber may be exempted frun being counted a3 inoperable. Generically susceptible stubbers are those which are of a specific make or model and have the same design features directly related to rejec-tion of the stubber by visual inspection, or are similarly located or exposed to the same environmental conditions, such as tenperature, radiation and vibration.

To provide assurance of stubber functional reliability, a representative sample of the installed srubbers will be functionally tested during plant shutdowns at 18 month intervals. Observed failures of these sample snubbers shall require evalua-tion and testing of additional units.

'Ihe service life of a srubber is evaluated via marufacturer input and information through consideration of the srubber service ccnditicns and associated installation ard maintenance records (newly installed srubber, seal replaced, in high radiation area, in high temperature area, etc. . . . .). The requirenent to monitor the

> rubber service life is included to ensure that the srubbers periodically undergo a performance ovaluation in view of their age and operating corxiitions. These recortis will provide statistical bases for future consideration of srubber service life.

The mquirements for the mairtenance of records and the sruMmr service life review are not intended to affect plant operation.

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d. Records of radiation exposure for all individuals entering radiation control areas.

e. Records of gaseous and liquid radioactive material released to the environs.

f. Records of transient or operational cycles for those facility ccr:ponents identified in Table 5.7-1.

g. Records of training and qualification for current mernbers of the plant staff,

h. Records of in-service inspections perfortned pursuant to these Technical Specifications.

i. Records of Quality Assurance activities identified in the NRC approved QA Manual as lifetime records.

j. Records of reviews perforTned for changes made to procedures or equipnent or reviews of tests and experiments pursuant to 10 CFR 50.59.

k. Records of meetings of the POSRC and the OSSRC.

1. Records of Envircrrnental Qualification which are covered t_%r the provisions of paragraph 6.13.

m. Records of the service lives of all snubbers listed on Table 3.7-l. in-cluding the date at which the service life ccr:rnences and associated installation and mainternnce records.

6.11 RADIATION PROTECTION PROGFW ,

Procedures for personnel radiation protection shall be prepared consistent with the requirenents of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.

l 6.12 HIGH RADIATIO 1 AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR Part 20:

a. A high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mren/hr shall be barricaded and conspic-uously posted as a High Radiation Area and entrance thereto shall be con-trolled by issuance of a Special or Radiation Work Permit and any individual or group of individuals permitted to er.ter such areas shall be provided with a radiation monitoring device which contiruously indicates the radia-tion dose rate in the area.

CALVERT CLIFFS - UNIT 14 I) NIT 2 6-20 I i