ML20083G892

Amend 19 to License NPF-12,correcting Administrative Errors in Tech Specs Involving Typographical Errors & Incorrect Plotting of Rod Bow Penalty Curve Data

ML20083G892
Person / Time
Site:	Summer
Issue date:	12/23/1983
From:	Adensam E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20083G894	List: ML20083G892 ML20083G896
References
NUDOCS 8401120443
Download: ML20083G892 (10)

Text

{{#Wiki_filter:,..... SOUTH CAROLINA ELECTRIC & GAS COMPANY SOUTH CAROLINA'PUBLIC SERVICE AUTHORITY DOCKET N0. 50-395 . VIRGIL C. SUPNER NUCLEAR STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.19 License No. NPF-12 l'. The Nuclear Regulatory Comission (the Comission) has found that: A. The application for amendment to the Virgil C. Sumer Nuclear Station, Unit No. 1 (the facility) Facility Operating License No. NPF-12 filed by the South Carolina Electric.& Gas Company acting for itself and South Carolina Public Service Authority (the licensc's), dated October 8, 1982, complies with the standards and requirements of the Atonic Energy Act of 1954, as amended (the Act) and the Comission's regulations as set forth in 10 CFR Chapter I; B.. The facility will operate in conformity with the application, as amended, the prov.isions of the Act, and the regulations'of the Comission; C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering th? health and safety of the public, and (if t that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I D. The issuance of this license amendment will not be inimical to the comon defense and security or to i.he health and safety of the public; E. The issuance of this license amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, ttie lic'ense is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment and paragraph 2.C(2) of. Facility Operating License No. NPF-12 is hereby amended to read as -follows: (2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.19, are hereby incorporated into this license. South Ca'rolina Electric & Gas Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan. 8401120443 831223 PDD ADOCK 05000395 P PDR =

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This license amendn:ent is effective as of its date of issuance. FOR TPE NUCLEAR REGULATORY COMMISSION h Elinor G. Adensam,' Chief -Licensing Branch No. 4 Division of Licensing

Enclosure:

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4 4 ATTACHMENT T0' LICENSE AMENDMENT NO. 19 FACILITY OPERATING LICENSE NO. NPF-12 DOCKET NO. 50-395 i Replace the following pages _of _ the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertica; lines indicating the area of change.. The corresponding over- - leaf pages.are also provided to maintain document completeness. Amended Overleaf Page Page 3/4 2-11 3/4 2-12 3/4 4-5 3/4 4-6 3/4 8-18 3/4 8-17 . 3/+ 9-9 3/4 9-10 t a 5 9 t -c.~ -t,, ,,r.. ..ww- -v ~w ,wy_--.m, y.-~w,--,----e,,

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M \\ SUttER - UNIT 1 3/4 2-11 Amendment No. 19

POWER DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02. APPLICABILITY: MODE 1 above 50% of RATED THERMAL POWER

• ACTION:

a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09: 1. Calculate the QUADRANT POWER TILT RATIO at least once per hour until either: a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER. 2. Within 2 hours either: a) Reduce the QUADRANT POWER TILT RATIO to within its limit, or b) Reduce. THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1.0 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours. 3. Verify that the QUADRANT POWER TILT RATIO is within its limit within 24 hours after exceeding. the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours and reduce the Power Range Neutron Flux-High Trip setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours. 4. Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL power may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours or until verified acceptable at 95% or greater RATED THERMAL POWER.

• See Special Test Exception 3.10.2.

SUMMER - UNIT 1 3/4 2-12 ~

1 I REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.1 At least one residual heat removal (RHR) loop shall be OPERABLE and in operation", and either: a. One additional RHR loop shall be OPERABLE, or b. The secondary side water l'evel of at least two steam generators shall be greater than 10 percent of wide range indication. APPLICABILITY: MODE 5 with Reactor Coolant loops filled ACTION: a. With less than the above required loops OPERABLE and/or with less than the required steam generator level, immediately initiate corrective action to return the required loops to OPERABLE status or to restore the required level as soon as possible. b. With no residual heat removal loop in operation, suspend all operations involving a reduction in boron concen-tration of the Reactor Coolant System and immediately initiate corrective action to return the required residual heat removal loop to operation. SURVEILLANCE REQUIREMENTS 4'.4.1.4.1.1 The secondary side water level of at least two steam generators when required shall be determined to be within limits at least once per 12 hours. 4.4.1.4.1.2 At least one RHR loop shall be determined to be in operation and circulating reac' tor coolant at least once per 12 hours.

1. 0ne residual heat removal loop may be inoperable for up to 2 hours for '

surveillance testing provided the other RHR loop is OPERABLE and in operation.

1. 1. A Reactor Coolant pump shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 300 F unless

1) the pressurizer water volume is less than 1288 cubic feet and/or 2) the secondary water temperature of each steam generator is less than 50 F above each of the Reactor Coolant System cold leg temperatures.

AThe RHR pump may be de-energized for up to 1 hcur provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at least 10 F below saturation temperature. SUMMER - UNIT 1 3/4 4-5 Amendment No.19

. REACTOR COOLANT SYSTEM COLD SHUTDOWN - LOOPS NOT FILLED LIMITING CONDITION FOR OPERATION 3.4.1.4.2 Two residual heat removal (RHR) loops shall be OPERABLE # and.at least one RHR loop shall be in operation.* APPLICABILITY: MODE 5 with Reactor Coolant loops not filled. ACTION: a. With less than the above required loops OPERABLE, immediately initiate corrective action to return the required loops to OPERABLE status as soon as possible. b. With nc RHR loop in operation, suspend all operations involving a reduction in boron concantration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation. i SURVEILLANCE REQUIREMENTS 4.4.1.4.2.1 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours.

1. 0ne RHR loop may be inoperable for up to 2 hours for surveillance testing provided the other RHR loop is OPERABLE and in operation.

A The RHR pump may be de-energized for up to I hour provided 1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and 2) core outlet temperature is maintained at least 10 F below satur'ation temperature. \\ SUMMER - UNIT 1 3/4 4-6 l 1

.wa. ~....... - ...~. ~ Ej._ECTRICAL POWER SYSTEMS / SURVEILLANCE REQUIREMENTS (Continued) (c) For each circuit breaker found inoperable during these functional tests, an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested. 2. By selecting and functionally testing.a representative sample of at least 10% of each type of lower voltage circuit breakers. Circuit breakers selected for functional testing shall be selected on a. rotating basis. Testing of these circuit breakers shall consist of injecting a current in excess of the breakers nominal setpoint-and measuring the respnnse time. The measured -response time will be compared to the manufacturer's data to insure that it is less than or equal to a value specified by the manufacturer. Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation. For each circuit breaker found inoperable during these functional tests, an additional repre-sentative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested. 3. By selecting and functionally testing a representative sample of each type of fuse on a rotating basis. Each representative sample of fuses shall include at least 10% of all fuses of that I type. The functional test shall consist of a non-destructive resictance measurement test which demonstrates that the fuse meets its manufacturer's design criteria. Fuses found inoperable i during these functional tests'shall be replaced with OPERABLE fuses prior to resuming operation. For each fuse found inoperable during these functional tests, an additional representative sample of at least 10% of all fuses of that type shall be functionally tested until no more failures are found or all fuses of that type have been functionally tested. l~ b. At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations. SUMMER - UNIT 1 3/4 8-17 4 _~ ._.. ~.__._ _ _. _ _. - _.. _ _ _. _ _ _.., _. _ _. _. _. _. -. -. _ - _ _ _ _. _ _ _

8 TABLE 3.8-1 a id 7 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICE TEST SETPOINT CRITERIA s EQUIP NO.-SYS/ DESCRIPTION DEV. ICE LOCATION TEST SETPOINT RESPONSE TIME 7.2 KV Swgr. 1) XPP0030A-RC PRIMARY XSW1A #9 LONG TIME 3960 Amps 5 15.75 Sec. Reactor Coolant Pump A INSTANT 5805 Amps N/A GROUND INST. 11 Amps .N/A BUS 1A Nornal Feed BACKUP XSW1A #5 LONG TIME 5544 Amps 5 15.33 Sec. BUS 1A Emergency Feed BACKUP XSW1A #3 LONG TIME. 5544 Amps 5 15.33 Sec. 2) XPP00308-RC PRIMARY XSW1B #7 LONG TIME 3960 Amps 5 15.75 Sec. w1 Reactor Coolant Pump B INSTANT 5808 Amps N/A 9 GROUND INST. 11 Amps N/A 5 BUS 1B Normal Feed BACKUP XSW1B #5 LONG TIME 5544 Amps 5 15.33 Sec. BUS 1B Emergency Feed BACKUP XSW1B #3 LONG TIME 5544 Amps 5 15.33 Sec. 3) XPP0030C-RC PRIMARY XSW1C #3 LONG' TIME 3960 Amps 5 15.75 Sec. Reactor Coolant Pump C INSTANT 5808 Amps N/A GROUND INST. 11 Amps N/A BUSIC Normal Feed BACKUP XSWIC #9 LONG TIME 5544 Amps 5 15.33 Sec. iy BUSIC Emergency Feed BACKUP XSWIC #13 LONG TIME 5544 Amps 5 15.33 Sec. g -t__..... %m

REFUELING OPERATIONS 3/4.9.8 REACTOR BUILDING PURGE SUPPLY AND EXHAUST ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.8 The Reactor Building Purge Supply.and Exhaust Isolation System shall be OPERABLE. APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment. ACTION: With the Reactor Building Purge Supply and Exhaust Isolation System inoperable, close each of the Purge and Exhaust penetrations providing direct access from the reactor building atmosphere to the outside atmosphere. The provisions of Specification-3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.9,8 The Reactor Building Purge Supply and Exhaust Isolation System shall be demonstrated OPERABLE within 100 hours prior to the ' start of and at least once per 7 days during CORE ALTERATIONS by veriflying that Reactor Building Purge ] Supply and Exhaust isolation occurs on manual initiation, on a high radiation test signal from each of the containment' radiation monitoring instrumentation channels, and by verifying that isolation occurs on the 36-inch lines of the Purge Supply and Exhaust Isolation System on a high radiation test signal from the reactor building manipulator crane area channels. SUMMER - UNIT 1 3/4 9-9 Amendment No. 19

e _REFUELXNG OPERATIONS 3/4.9.9 WATER LEVEL - REFUELING CAVITY AND FUEL TRANSFER CANAL 4 ~ . LIMITING CONDITION FOR OPERATION ~. 3.9.9 At least 23 feet of water shall be maintained over the top of the reactor pressure vessel flange. APPLICABILITY: During movement of fuel assemblies or control rods within the reactor pressure vessel or the refueling cavity when either the fuel assemblies being moved or the fuel assemblies seated within the reactor pressure vessel are irradiated.' ACTION: With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the pressure vessel. SURVEILLANCE RE0VIREMENTS 4.9.9 The water level shall be determined to be at least its minimum re, quired depth within 2 hours prior to the start of and at least once per 24 hours thereafter during movement of fuel assemblies or control rods. o e e e Og I t 5%,;;ER - UNI.T,.1, 3/4 9-10 s ..v m ,}}