ML20059B720

Amend 141 to License DPR-16,revising Tech Specs to Accomodate Implementation of 21-month Cycle w/3-month Outage or 24-month Refueling Cycle for Tech Spec Surveillances That Will Expire Prior to Current Refueling Outage 13R

ML20059B720
Person / Time
Site:	Oyster Creek
Issue date:	08/20/1990
From:	Stolz J Office of Nuclear Reactor Regulation
To:	GPU Nuclear Corp, Jersey Central Power & Light Co
Shared Package
ML20059B722	List: ML20059B720 ML20059B725 ML20059B729
References
DPR-16-A-141 NUDOCS 9008300025
Download: ML20059B720 (12)

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• j, WASHINoToN, o. C. 20555 f-p GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 OYSTER CREEK NUCLEAR GENERATING STATION AMEN 0 MENT TO PROVISIONAL OPERATING LICENSE Amendment No. 141 License No. DPR-16 1

1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by GPU Nuclear Corporation, et al., (the licensee), dated May 4, 1990 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; 8. 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) t.% c such. activities will be conducted in compliance with the Commission's regulations; l D. The issuance of this amendment will not be inimical to the common l 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. l-9008300025 900820 ADOCK050g29 PDR P W +- m-

l ., t L 2. Accordingly, the license is amended by changes to the Technical ol" Specifications as' indicated in the attachment to this license amendment, I and paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows: I (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amer.dment No.141, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications. 3. This license amendment:is effective as of the date of issuance. FOR THE~ NUCLEAR REGULATORY COMMISSION hn h Stolz, Director r ect Directorate I-4 ' ision of P.eactor Projects - I/II -Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications -Date of Issuance: ' August 20, 1990

ATTACHMENT TO LICENSE AMENDMENT NO.141 PROVISIONAL OPERATING LICENSE NO. DPR-16' D0CKET NO. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change. Remove Insert Page 4.1 Page 4.1-6 Page 4.1-8 Page 4.1-8 Page-4.2-2 Page 4.2-2 Page 4.5-3 Page 4.5-3 Page 4.5-6 Page 4.5-6 Page 4.5-9 Page 4.5-9 Page 4.5-11 Page 4.5-11 -Page 4.7-1 Page 4.7-1 Page 6-16 Page 6-16 6 e i w -.11.-

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TABLE'4.1.1'(cont *d) n I 'E N Instrument ch m l check Calibrate Test Remarke (Apolies to Test and Calibrationn

11. APRM Level N/A 1/3'd N/A Output adjustment using operational type heat balance-during power operation APRM Scram Trips Note 2 1/wk.

1/wk. Using built-in ca,bration equipment during power operation

12. APRM Rod Blt.,cke Note 2 1/3 mo.

'1/mo. Upecale and downecale i 13.a. High Radiation in Main Steamline 1/e 1/3 mo. 1/mo. Using built-in calibration equipment i during power operation

b. Sensore for 13(a)

N/A Each re-N/A Using external radiation source fueling outage

14. High Radiation in Reactor Building Operating Floor 1/e 1/3 mo.

1/wk Usig gamma source for calit ,lon Ventilation Exhaust 1/e 1/3 mo. 1/wk. Using g - source for calibration

15. High Radiation on Air Ejector 1/3 mo.

1/wk. Using built-in calibration equipment. [t*g Ejector Off-Gas 1/e Channel check ! g 1/mo. l [ g source check 1/24 mo. i g Calibration according to established station calibration procedures r' 2: 1/24 mo. Note a o

16. IRM Level N/A Each N/A startup IRM Scram Using built-in calibration equipment a

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o 2 4 TABLE 4.1-1-(cont'd) _ t Instrument ch====1 Check Calibrate' Test Q-Pemarks (Applies To Test and Calibrationi N 27. Scram Discharge Volume (Rod Block) -i a) Water level N/A Each re-Every 3 By varying level in switch column high fueling months outage b) Scram Trip bypass N/A N/A Each re-fueling outage

28. Loss of Power a) 4.16 KV Emergency Bus

. Daily 1/24 sos. 1/mo. Undervoltage 8 (Loss of voltage) c. -[s b) 4.16 KV Emergency Bus Daily 1/24 mos. 1/mo. Undervoltage L (Dograded Voltage) i

29. Drywell High N/A Each re-Each re-l Radiation f

fueling feeling l outage outage I I n w i [ ga calibrate prior to startup and normal shutdown and thereafter check 1/s and test 1/wk until no-longer required. { J Leoend: N/A = Not Applicable; 1/s = Once per shift I 1/d = Once per day; 1/3d = Once per three days; 1/wk = Once per wet g 1/3 mo = Once every 3 months; 1/18 mos. = onze every 18 months, 1/24 = Once per 24 sonthe [ m

• The following notes are only for Item 15 of Table 4.1.1:

I A channel may be taken out of service for the purpose of a check, calibration, channel to be inoperable. test or maintenance without declaring the The channel functional test'shall also demonstrate that control room alarm annunciation occurs if any of the'fo a. conditions exists: k I

1) Instrument indicates measured levels above the alarm setpoint.-

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2) Instrument indicates a downscale failure.

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3) Instrument controle not set in operate sede.

4) Instrument. electrical power ~1oss.

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'3. Functien21't0st Cncs cv0ry 24 months {! 't s 4. solutien volume and on:3/ day temperature check 5. Solution Boron-10 Each refueling outage. l enrichment Enrichment analyses shall be received no later than 30 days after startup from the refueling outage. If not' received within 30 days, notify NRc (within 7 days) of plans to obtain test results. j F. At specific power operation conditions, the actual control rod configuration will be compared with the expected configuration based upon appropriately corrected past data. This comparison shall be made every equivalent full power month. The initial rod inventory j measurement performed with equilibrium conditions are established after. ] a refueling or major core alteration will be used as base data for i reactivity monitoring during subsequent power operation throughout the fuel cycle. t G. The scram discharge volume drain and vent valves shall be verified open least once per 31 days, except in shutdown modea, and shall be at cycled at least one complete cycle of full travel at least quarterly. H. All withdrawn control rods shall be determined OPERABLE by demonstrating th6 scram discharge volume drain and vent valves OPERASLE. This will be done at least once per refueling cycle by-placing the mode switch in shutdown and by verifying thats The drain and vent valves close within 30 seconds after receipt of a. a signal for control rods to scram, and i b. The scram signal can be reset and the drain and vent valves open 1-when the scram discharge. volume trip is bypassed. I BASIS: The core reactivity limitation (specification 3.2.A) requires that s core reactivity be limited such that the core could be made y L suberitical at any time during the operating cycle, with the-strongest operable control rod fully withdrawn and all other operable rods fully inserted. Compliance with this requirement can be demonstrated conveniently only at the time of refueling. Therefore, the demonstration must be such that it will apply to the entire subsequent fuel cycle. The demonstration is performed with the reactor core in the cold, xenon-free condition and will show

• These valves may be closed intermittently for testing under administrative control.

l 1 Corrected: 12/24/84 OYSTER CREEK 4.2-2 Amendment No.: 64, 74, 7 d, 124, 141 Change: 25 ' y

- - - -~ -- ~ ~~ ~ ^~~ Di-Freruancy 0

1. Thro 3 Type 'Acycrall Intcgrcted Containment Leikag3 Rate Tests shell be conducted at approximately 40 month intervals during scheduled shutdowns within each 10-year j

service period. The third test of each set shall be conducted during the shutdown for the 10 year plant inservice inspection.

2. If two consecutive periodic Type A tests fail to meet the acceptance criteria, the subsequent Type A test shall be performed at each shutdown for refueling or approximately every 18 months whichever occurs first.

This schedule-will remain in effect until two consecutive Type A tests meet the acceptance criteria, at which time the frequency of testing noted in D.1 above may be resumed. E. Tyne "B" and "c" Local Leah Rate.,23agg _ m

1. Primary containment testable penetraM ons (Type "S" Test) and isolation volves (Type "C" Test),'except as stated below, shall be tested at a pressure of least 35 poig (P ) at intervals not to exceed 24 months.

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2. The main steam line isolation valves shall be tested at a pressure of at least 20 peig at intervals not to. exceed t

24 months to determine if corrective action is required.

3. Isolation valve, Type "C", tests shall have each valve.

closed by normal operation. (e.g. no preliminary exercising or tightening of valve after closures by valve motor).

4. Bolted double gasketed seals shall be tested whenever the seal is closed after being opened,-and at intervals:not to exceed 24 months.

t 5.' The drywell airlock shall be demonstrated operable by performing the following tests: i OYSTER CREEK 4.5-3 Amendment No.: 43f", 141 Change No.: 7

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4. Mna to Sumeraamien ch==har Vaeuuni Brenhara I

.c. Th3 rotetsr building to suppr00sian chamber vacuum break 0re end r asecalated instrumentation, including setpoint, shall.be checked for proper operation every three months.

b. Once every 24' months each vacuum breaker shall be tested to l

determine that the force required to open the vacuum breaker 7 from' closed to fully.open does not exceed the force specified in specification 3.5.A.4.a. The air-operated vacuum breaker 3' instrumentation shall be calibrated once every 24' months. l t

5. Preasure Sumeraamien Chamker - Drvwell Vacuum Breakers

a. Periodie Deerability Tants once each nonth and following any release of-energy which would tend to increase pressure to the suppression chamber, each operable suppression chamber - drywell vacuum breaker shall be exercised. Operation of position switches, indicators and alarms shall'be verified monthly by operation of each operable vacuum breaker.

b. Tests - once Every 24 Months L

(1) All suppression chamber - drywell vacuum breakers'shall be tested to determine the force required to open each valve from fully closed to fully open. (2) The suppression chamber - drywell vacuum breaker position indication and alarms systems shall be calibrated and functionally tested. (3) At least four of the suppression chamber - drywell vacuum breakers shall be inspected. If deficiencies are found, all vacuum breakers shall be inspected and deficiencies corrected such that specifications 3.5.A.5.a can be met. t

c. Testa - once Every 2u Months A drywell to suppression chamber leak rate test shall demonstrate that with an initial differentia 1' pressure of not less than 1.0 psi,'the differential pressure decay rate shall not exceed the equivalent of air flow through a 2-inch orifice.

l K. Remeter Buildina L

1. Secondary containment capability tests shall be conducted after isolating the reactor building and placing either Standby cas i

L Treatment system filter train in operation. 1 r

2. The testa shall be performed at least once per operating cycle and shall demonstrate the capability to maintain a inch of i

water vacuum under calm wind conditions with a Standby Gas Treatment System Filter train flow rate of not more than 4000 cim. OYSTTR CREEK 4.5-6 Amendment No.4 J47 J46 ))f's 101

~ 1 Q,, Sheek Bunersamera (Enuhkerel ,1

1. Each snubber shS11 be demon:tratCd cperable by performance of the following inspection program:

4. Visual Inaneetiens All snubbers shall be' visually inspected in accordance with the following schedule .No. Inoperable Snubbers' Subsequ3nt Visual Per Inanection Period Inanection pee 12d* O 24 months 1 25% l. 1 12 months 1 25% l 2 6 months 1 25% 3, 4 124 days i 25% 5,6,7 62 days 1 25% 8 or more 31 days 1 25%

• The provisions of Technical specification 1.24 are not i

i applicable. l l The required inspection interval shall not be lengthened more than one step at a time. The snubbers may be l l' categorized into two groups: those accessible and those inaccessible during reactor operation. Each group may be inspected independently,in accordance with the above schedule. b. Visual Innometion Accentance criteria Visual inspections shall verify (1) that there are no visible indications of damage or impaired OPERABILITY, j (2) attachments to the foundation or supporting i structure are secure,.and (3) in those locations where snubber movement can be manually induced without ' disconnecting the snubber, that the snubber has freedom s of movement and is not seized. 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 the L affected snubber is functionally' tested in the as-found condition and determined operable per specification 4.5.Q.d or 4.5.Q.e as applicable and that the cause for the rejection has been clearly established and remedied for that particular snubber. c. Functional Testa At least once every 24 months, a representative sample I (10% of the total of each type of snubber in use in_the plant) shall be functionally tested either in place or q in a bench test. For each snubber that 1 ' OYSTER CREEK 4.5-9 Amendment No.: 1A, 32, St',1DO, JJ11 141 --s-

C. Machanical anubbara Functional tant Aeemetanea critaria-f , Th3 methanic31 anubber functional test shall verify that 1..The force that initiated free movement of the snubber rod ~ in either tension or compression is less than the specified maximum drag force.-

2. Activation (restraining action) is achieved'within the specified range of velocity or acceleration in both tension and compression.

3. snubber release rate, where required, is within the specified range in compression or tension. -For snubbers

,[ specifically required not to displace under continuous. load, the ability of the snubber to withstand load without displacement shall be verified.- f. Snubber servien Life Monitorine A record of the service life of each snubber, the date at which the dos,ignated service life commences and the installation and maintenance records on which the designated service life is based shall be maintained as required by Specification 6.10.2.1. 1 concurrent with the first inservice visual-inspection and at i least once per-24 months thereafter, the installation and-l maintenance records for each snubber shall be reviewed to i verify that the indicated service life has not been exceeded or will not be exceeded prior to the next scheduled snubber service life review. If the indicated service life will be exceeded prior to the next scheduled snubber service life review, the snubber service life shall be re-evaluated or the snubber shall be replaced or reconditioned so as to i extend its service life beyond the date of the next scheduled service life-review. This re-evaluation, replacement or reconditioning shall be indicated in-the L records. Service life shall not at any time affect reactor operations. t -{ s. = OYSTER CREEK 4.5-11 Amendment No.: 10'O, 12f' 141

v ..'4.7 AUZILIARY EL$cTRICAL POWER y ' ~ l Ane11emb111tvs. Applies to survoillenco r;quirements of tho auxilicry electrical suppif.- ohdectives: To verify the availability of the auxiliary electrical , supply., Boecification s. A. Dianal canarator i.

1. Each diesel generator shall be started 'and loaded to not less than 20% rated power every two weeks.

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2. The two diesel generators shall be automatically

\\ actuated and functionally' tested once every 24 months.- This shall include testing of the diesel -f' generator load sequence timers listed in Table 3.1.1.

3. Each_ diesel generator shall be given a' thorough inspection at least once per 24 months during shutdown.

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4. The diesel generators' fuel supply shall be checked following the above tests.

5. The diesel generators' starting batteries shall be tested and monitored the same as the station I

' batteries, specification 4.7.b.

3. Station Batterie,3 l

1. Weekly surveillance will be performed to verify the I

followings i F

a. The active metallic surface of the plates shall be fully covered with electrolyte in all batteries,

b. The designated pilot cell voltaae is greater

[ than or equal to 2.0 volte and ~!

c. The overall battery voltage is greater than or

~ i equal to 120 volts (Diesel-battery; 112 volts).- 5

d. The pilot cell specific gravity, corrected to 77'F, is greater than or equal to 1.190.

t 2.. Quarterly surveillance will be performed to verify l the following: 1 I

a. The active metallic surface of the plates shall be fully covered with electrolyte in all-batteries.

p . b. The voltage of each connected cell is greater than-or equal to 2.0 volts under float charge and -OYSTER CREEK 4.7-1 Amendment No.: J4I #5I,56's I41 1

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4.7l AUZILIARY EIApTRICAL POWER

,r ~. ~ Ann 11eah111tv: = Appli:s to surv3111cncy requiremento of th3 cuxiliary. f = electrical supply. obiective: To verify the-availability of the auxiliary electrical Y supply.. Snacificatient' A. Dianal canarater

1. Each diesel. generator shall be started ~and ' loaded to not less than 20% rated power every two weeks.

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2. The two diesel generators shall be' automatically.

actuated and= functionally tested once every 24 l' months. This shall include testing of the diesel I* ~ generator load sequence timore listed in Table 3.1.1.

3. Each diesel generator shall be given a thorough inspection at least once per 24 months during shutdown.

[,

4. The diesel generators' fuel supply shall be checked following the above toets.

5. The diesel generators' starting batteries shall be tested and monitored the same as the station batteries, specification 4.7.b.

3. Station Batteries

1. Weekly. surveillance will be performed to vselfy the followings i

a. The active metallic surface of the plates shall be. fully covered with electrolyte in all'

-batteries, ~b. The designated pilot cell voltage is greater than or equal to 2.0 volts and'

c. The overall battery voltage is greater than cur

- t equal to 120 volts (Diesel-battery; 112 volts)..

d. The pilot cell specific gravity, corrected to

.i 77'F, is greater than or equal to 1.190.

2. Quarterly Surveillance will be performed to verify the followings

a. The active metallic surface of the plates shall

.txe fully covered with electrolyte in all batteries. . b. The voltage of each connected cell is greater than or equal to 2.0 volto under float charge and OYSTER CREEK 4.7-1 Amendment No.: % M,d> 141

e-activitios within tho ar00 and wha will perform periodic radiation surveillance at the frequency in the RWP. The surveillance frequency will be established by the Director responsible for Radiological Controls. 6.13.2 specification 6.13.1 shall also apply to each'high radiation area in which the intensity of radiation is greater than 1,000 mrom/hr. ' addition, locked doors shall be provided to prevent unauthorised entry ini r t.ch areas and the keys shall be maintainod under the administrative contref operations and/or radiation protection supervision on duty. 6.14 ENVIRONMENTAL QUALIFICATION A. By.no later than June 30, 1982 all safety-related electrical equipment in the facility shall be qualified in accordance with the provisions of: Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or, NUREG-0588 " Interim Staff Position on Environmental Qualification of safety-Related Electrical Equipment," December 1979. Copies of these documents are attached to order for Modification of License DPR-16 dated October 24, 1980. B. By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Cuidelines or HUREG-0588. Thereaf ter, such records should be updated and maintained - current as equipment is replaced, further tested, or otherwise further qualified. ~ 6.15 INTEGRITY OF SYSTEMS OUTSIDE CONTAINMENT The licensee shall implement a program to reduce leakage from systems outside containment that would or could contain highly radioactive fluida during a serious transient or accident to as low as practical levels. This program shall include the following:

1) Provisions-establishing preventative maintenance and periodic visual inspection requirements, and

2) system leak test requirements, to the extent permitted by system design and radiological conditions, for er.ch system at a frequency of once every 24 months. The systems subject to this testing are (1) Core Spray, (2)

Containment Spray, (3) Reactor Water cleanup, (4) Isolation condenser, and (5) Shutdown Cooling. s. 6.16 IODINE MONITORING The licensee shall implement a program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas

• under accident conditions. This program shall include the followings a.

Training of personnel,

• Areas requiring personnel access for establishing hot shutdown condition.

OYSTER CREEK 6-16 Amendment No.: 6d,10),}34'.141}}