ML20100R759

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Proposed TS 3/4.8.1 Re Electrical Power Sys - A.C. Sources
ML20100R759
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 03/08/1996
From:
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20100R757 List:
References
NUDOCS 9603120516
Download: ML20100R759 (7)
v • d • e


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' Attachment II to WO 96-0037 l

.Page 2 of 8 ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 0.'fr';in; the 'h: rute := r rd '^rd: t: erh ter';rree-hgc. giCSC(

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6) Verifying fullIEad carrying capabilityof the diesel generator werwkor o f " N '*

at a power factor between 0.8 and 0.9 for ar' interval of not less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 5580 to 6201 kW (indicated)*. The generator

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s voltage and frequency shall be maintained within 160 + 160 gdl<,.c Y< cl Weo O to 420 volts and 6011.2 Hz during this test; a#K

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7) Verifying the diesel generator's hot restart capability by operating 5-o *
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the diesel generator for greater than or equal to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at an s e c.c en.5 <. abov e.

l Indicated load of 5580 to 6201 kW, shutting down the diesel yg( g*

l generator and restarting it within 5 minutes. On restart, the diesel generator voltage and frequency shall be 4160 + 160 - 420 volts and 6011.2 Hz within 12 seconds after the start signal; l

8) B) Venfying the diesel generator's capabilit ** to:

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a) Synchronize with the offsite power source while the generator 1

is loaded with its emergency loacs upon a simulated restoration of offsite power.

b) Transfer its loads to the offsite power source. and c) Be restored to its standby status.

9) 40) Venfying that with the diesel generator operating in a test mode, connected to its bus, a simulated Safety injection signal overrides the test mode by: (1) retuming the diesel generator to standby operation and (2) automatically energizing the emergency loads with offsite power; 10)

Verifying that the fuel transfer pump transfers fuel from each fuel storage tank to the day tank of each diesel via the installed cross-connectionlines; and 11)

Venfying that the automatic LOCA and Shutdown sequence timer is OPERABLE with the interval between each load block within

~ 0% of its design intervat.

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h. At least once per 10 years verify that when statted simultaneously l

from standby conditions," each diesel generator achieves in less than or equal to 12 seconds, a voltage of 4160 + 160 - 420 volts and a frequency of 6011.2 Hz.

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'This surveillance shall not be performed in Modes 1, or 2 and credit g,r,[,,,.

\\ t< WiuhwMe f" s o.3 sy_be taken for unplannedg_that satisfy this_Jpquirement.

a "This test snall be precedec Uy an engine prelube penod and/or otherwarmup 1

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procedures recommended by the manufacturer so that the mechanical stress and W M "U

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bu s ( o c.,d 5 Sk% dob r en the diesel enginefs_ minimized.

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"*This surveill nce shall not be performed in Modes 1,2,3, or 4 and credit

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,#y ay be taken for unplanned events that satisfy this requirement.

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WOLF CREEK UNIT 1 3/4 8-6 Amendment No 8 9603120516 960308 PDR ADOCK 05000482 P

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Attachment II to WO 96-0037

.Page 3 o,f 8 ADMINISTRATIVE CONTROLS MEETING FREQUENCY 6.5.1.4 The PSRC shall meet at least once per calendar month and as convened by the PSRC Chairman or his designated attemate.

QUORUM 6.5.1.5 The quorum of the PSRC necessary for the performance of the PSRC responsibility and authonty provisions of these Technical Specifications shall consist of the Chairman or his designated attemate and four members including altemates.

RESPONSIBILITIES 6.5.1.0 The PSRC shall be responsible for.

a. Review of: (1) Administrative Control Procedures and changes thereto, and (2) procedures and changes thereto requitect by Specification 6.8.1 and requiring a 10 CFR 50.59 safety evaluation.

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b. Review cf all proposed changes, tests and expenments which may involve an unreviewed safety question as defined in Section 50.59.

10 CFR; Review of all proposed changes to Technical Specifications or the c.

Operating License;

d. Review of all safety evaluations performed under the provision of Section 50.59(a)(1),10 CFR, for changes, tests and expenments; i

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e. Investigation of all violations of the Technical Specifications includmg the preparation and forwarding of reports covenng evaluation and recommendations to prevent recurrence to the Vice President Plant Operations, and to the Nuclear Safety Review Committe.9 (NSRC);
f. Review of all REPORTABLE EVENTS; i

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g. Review of reports of operating abnormalities, deviations from expected performance of plant equipment and of unanticipated deficiencies in the design or operation of structures, systems or components that affect nuclear safety;
h. Performance of special reviews, investigations or analyses and i

reports thereon as requested by the Chairman, NSRC; #)

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j. Not used.

WOLF CREEK UNIT 1 6-8 Amendment No. 4M 73

4ttachmerit II to WO 96-0037 Page 4 of 8

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ADMINISTRATIVE CONTROLS AUDITS (Continued)

d. The performance of activities required by the Operational Quality Assurance Program to meet the entena of Appendix B,10 CFR Part 50, at least once per 24 months;
e. The fire protection programmatic controls including the implementing -

procedures at least once per 24 months by qualified licensee OA or ISEG personnel;

f. The fire protechon equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant. An outside independent fire protection consultant shall be used at least every third year;
g. The Radiological Environmental Monitonng Program and the results thereof at least once per 12 months;
h. The ODCM and implementing procedures at least once per 24 months:
i. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months;
j. The performance of activities required by the Quality Assurance Program for effluent and environmental monitonng at least once per 12 months;
k. The Emergency Plan and implementing procedures at least once per 12 months;
l. The Secunty Plan and implementing procedures at least once per 12 months;-and hm Any other area of Unit operation considered appropnate by the NSRC or the President and Chief Executive Officer;.

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RECORDS 6.5.2.9 Records of NSRC activities shall be prepared, approved, and distnbuted as indicated below;

a. Minutes of each NSRC meeting shall be prepared, reviewed by partici.

pating members and forwarded to the President and Chief Executive Officer within 14 days following each meeting;

b. Reports of reviews encompassed by Specification 6.5.2.7 above, shall be prepared, reviewed by participating members and forwarded to the -

President and Chief Executive Officer within 14 days following com-pletion of the review; and WOLF CREEK UNIT 1 6-12 Amendment No. 4

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Attachment II to WO 96-0037

.Page 5 o,f 8 j

ADMINISTRATIVE CONTROLS i

i Pf0CEDURES AND PROGRAMS (Continued)

e. Process Control Program implementation;
f. ODCM implementation:-and
g. Quality Assurance Program implementation for effluent and environ-mental monitonng; h7.

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6.8.2 Each procedure of Spoofication 6.8.1 and changes thereto; and any l

other procedure or procedure change that the Vice President Plant Operations I

determines to affect nuclear safety, shall be reviewed and approved as desenbed below, pnor to implementation.

a. Each procedure, or change thereto shall be reviewed by a Qualified Reviewer who is knowledgeable in the functional area affected, but is not the individual who prepared the procedure or procedure change. All required cross-disciplinary reviews of new procedures, procedure revisions or enange thereto shall be completed pnor to i

approval.

b. Procedures other than Administrative Control Procedures shall be approved by the responsible Manager or his designee as specified in Administrative Control Procedures. The Vice President Plant Operations shall approve Administrative Control Procedures. The Manager responsible for the Secunty Plan shall approve the Secunty Plan and implementing procedures. The Manager responsible for Emergency Planning shall approve the Radiological Emergency Response Plan and implementing procedures.
c. The responsible Manager or his designec shall ensure each review

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includes a determination of whether a procedure, or change thereto, l

requires a 10 CFR 50.59 safety evaluation. If a procedure, or change thereto, requires a 10 CFR 50.59 safety evaluation, tne responsible Manager or his designee shall forward the procedure, or change thereto with the associated 10 CFR 50.59 safety evaluation to the PSRC for review in accordance with Specification 6.5.1.6.a.

1 Pursuant to Section 50.59.10 CFR, NRC approval of items involving I

unreviewed safety questions shall be obtained pnor to approval for implementation.

d. Qualified Reviewers shall beet the applicable Qualifications of ANSl/ANS 3.1-1978. Personnel recommended to be Qualified Reviewers shall be reviewed by the PSRC and approved and documented by the PSRC Chairman. The responsible Manager shall ensure that a sufficient complement of Qualified Reviewers for their functional area is maintained in accordance with Administrative Control Procedures.
e. Records documenting the activities performed under Specification 6.8.2.a. through 6.8.2.d. shall be maintained in accordance with Specification 6.10.

WOLF CREEK UNIT 1 6-14 Amendment No. 4r15M 5, 59. 73 1 to WO 96-0037 Page 6 of 8 4

INSERT "A" The surveillance requirements of Technical Specification 3/4.8.1 are based upon, in part, the guidance of Generic Letter 94-01, " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators From Plant Technical Specifications," Genenc Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," Regulatory Guide 1.9,

" Selection. Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electrical Power Systems at Nuclear Power ~ Plants," Revision 3, and NUREG-1431,

- has been adopted to formulate a comprehensive Emergency Diesel Generator Reliability Program.

Technical Specification 3.8.1.1, Action b and c, require, in part, the demonstration of the operability of the remaining operable emergency diesel generator by performing Technical Specification 4.8.1.1.2a.4. This test is required to be completed regardless of when the inoperable emergency diesel generator is restored to operable status unless the emergency diesel generator was declared inoperable to do preplanned preventative maintenance, testing, or maintenance to correct a condition which, if left uncorrected, would not affect the operability of the emergency diesel gaaerator. The requirement to test the remaining operable emergency diesel generator when one emergency diesel generator is inoperable is limited to those situations where the cause for inoperability can not be conclusively demonstrated in order to preclude the potential for common mode failures. The test is not required to be accomplished if the emergency diesel generator was declared inoperable due to an inoperable support system or an independently testable component. When such a test is required, it is required to be performed within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of having determined that the emergency diesel generator is inoperable.

Technical Specification 4.8.1.1.2a.4 is considered to be a " Start Test" as described in Regulatory Guide 1.9, Revision 3. A " Start Test" is performed to demonstrate proper startup from standby conditions and to verify that the required design voltage and frequency is attained.' For these tests, Regulatory Guide 1.9, Revision 3, recommends that the emergency diesel generators be slow started and allowed to reach rated speed on a prescribed schedule that is selected to minimize stress and wear.

Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2a.5 to be a " Load-Run Test". A " Load-Run Test" demonstrates 90 to 100 percent (5580 to 6201 kilowatts) of the continuous rating (6201 kilowatts) of the emergency diesel generator for an interval of not less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and until temperature equilibrium has been attained. This test may be accomplished by synchronizing the generator with offsite power and the loading and unloading of an diesel generator during this test should be gradual and based on a F40:ribed schedule that is selected to minimize stress and wear on the diesel generator.

Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2b to be a ?=st-Start Test". A " Fast-Start Test" demenstrates that each emergency diesel generator starts from standby conditions. If a plant normally has in operation keep warm systems designed to maintain lube oil and Jacket water cooling at certain temperatures or prelubrication systems or both, this would constitute normal standby conditions for that plant. Verification that the emergency diesel generator reaches required voltage and frequency within acceptable limits and time is also required.

The requirements of the " Single-Load Rejection Test" and the " Full-Load Rejection Test" as described in Regulatory Guide 1.9, Revision 3 have been combined. The " Full-Load Rejection Test" is a demonstration of the emergency diesel generator's capability to reject a load equal to 90 to 100 percent of its continuous rating (5580 to 6201 kilowatts) while operating at a power factor between 0.8 and 0.9 and that the voltage does not exceed 4784 volts and that the frequency does not exceed 65.4 Hertz following a load rejection of 5580 to 6201 kilowatts. The frequency criteria is from the " Single-Load Rejection Test" and is based on nominal en ine s I 75 reent of

'"=p between_nomingsgeed and the ovelspeed trip setDoint in a i on, through a pl nt ure, the ESW pump starting transient during the LOCA sequehci6g Test, Technical Specification 4.8.1.1.2.g.4.d, will be demonstrated to be within a minimum voltage of 4784 Vac and recover to 4320 Vac within 3 seconds and to be within a maximum voltage of 4784 Vac and recover to 4320 Vac within 2 seconds. This acceptance criteria is based on Regulatory Guide 1.9 Revision 3, section 1.4 and past trending *of ESW pump starting The note that will not allow a surveillance requirement to be performed in Modes 1 or 2 is based on the improved Standard Technical Specifications (NUREG-1431) which recognizes that the performance of certain surveillance requirements during operation with the reactor critical could cause perturbations to the electrical distribution systems that could challenge continued steady state operation and, as a result, unit safety systems. However, this note does not preclude operating the emergency diesel generator with the reactor entical, as necessary, to support operational conditions.

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. 1 to WO 96-0037 Page 7 of 8 INSERT "B" DIESEL FUEL OIL TESTING PROGRAM in accordance with Technical Specification 6.8.4, a Diesel Fuel Oil Testing Program to implement required testing of both new fuel oil and stored fuel oil shall be established. For the intent of this specification, new fuel oil shall represent diesel fuel oil that has not been added to the Diesel Fuel Oil Storage Tanks. Once the fuel oil is added to the Dieset Fuel Oil Storage Tanks, the diesel fuel oil is considered stored fuel oil, and shall ineet the Technical Specification requirements for stored fuel oil.

Tests listed below are a means of determining whether new fuel oil is of the appropnate grade and has not been contaminated with substances that would have an immediate detnmental impact on diesel engine combustion, if results from these tests are within acceptable limits, the new fuel oil may be added to the storage tanks without concem for contaminating the entire volume of fuel oil in the storage tanks. These tests are to be conducted pnor to adding the new fuel to the storage tanks, but in no case is the time between receipt of the new fuel oil and conducting the tests to exceed 30 days. The tests, limits, and a b

TM stand rds being used to evaluate the conditic.n of new fuel oil are:

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By samplingnew fue oiQq;[ ASTM D4057 prior to addition to storage tanks and:

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By venfyin_ _ __ _ _ _,,,e tests specified in ASTM D975-81 pnor to addition to the storage tanks that the sample has:

a)

An API Gravity of within 0.3 degrees at 60 *F or a specific gravity of within 0.0016 at 60/60 *F. when compared to the supplier's certificate or an absolute specific gravity at 60/60 'F or greater than or equal to 0.83 but less than or equal to 0.89 or an API gravity of greater than or equal to 27 degrees but less than or equal to 39 degrees; b)

A kinematic viscosity at 40 *C of greater than or equal to 1.9 centistokes, but less than or equal to 4.1 l

centistokes, if gravity was not determined by compenson with the supplier's certification; c)

A flash point equal to or greater than 125 'F; and d)

A water and sediment content of less than or equal to 0.05% when tested based on ASTM D1796-83.

Failure to meet any of the above limits is cause for rejecting the new fuel oil, but does not represent a failure to meet the Limiting Condrtion for Operation of Technical Specification 3.8.1.1 since the new fuel oil has not been added to the j

diesel fuel oil i

Within 30 days following the initial new fuel oil sample, the fu[ oil is analyzed to establish that the other properties specified in Table 1 of ApTM D975-81 are met when tested ;C ; i ASTM D975-81 except that the analysis for sulfur may be performed seestHm ASTM D1552-79, ASTM D2622-82, or ASTM 04294-90. An exception to ASTM D129, which is specified in ASTM D975-81, has been taken. ASTM D129 uses a Banum precipitation method for the determination of sulfate after oxidation has occurred. The use of any wet lab sulfate analysis is acceptable since the I

determination is made in the aqueous nnte water for the oxidation process. In the event the correct fuel oil properties s

l are not met. Action g provides an additional 30 days from the time that it is determined that the correct fuel oil properties are not met to meet the Diesel Fuel Oil Testing Program limits. The additional 30 day penod is acceptable because the fuel oil properties of interest, even if they are not within limits, would not have an immediate effect on emergency diesel generator operation. The diesel fuel oil surveillance in accordance with the Diesqti Fuel Oil Testing Program Il ensure the availability of high quality diesel fuel oil for the emergency diesel generators. f g.;.ba We du.or o.m e i

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At lease once every 31 days, a sample of fuel oil is obtainad from the storag tanks M___ -, ASTM D2276-83. The particulate contamination is venfied to be less than 10 mg/ liter when checked t = r, ASTM D2276-83, Method A. The filter size for the determination of particulate contamination will be 3.0 micron instead of 0.8 micron as specified by ASTM D2276-83. The filtered amount of diesel fuel oil will be approximately one liter when possible. Also, it is acceptable to obtain a field sample for subsequent laboratory testing in lieu of field testing.

Fuel oil degradation during long term storage shows up as an increase in particulate, due mostly to oxidation. The presence of particulate does not mean the fuel oil will not bum properly in a diesel engine. The particulate can cause foulang of filters and fuel oilinjection equipment which can cause engine failure.

l The frequency for performing surveillance on stored fuel oil is based on stored fuel oil degradation trends which indicate 1

that particulate concentration is unlikely to change significantly between surveillances.

' Attachment 11 to WO 96-0037 Page 8 of 8 INSERT "C" -

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g. Dianal Fuel Oil Teatino Procram.

/# of Go 0MA 6b A diesel fuel oil testing program to implemen equired testing of both new fuel oil and stored fuel oil. The program s 1 include sampling and testing requirements, and acceptance entena. M a the applicable ASTM t

Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

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1. an API gravity or an absolute specific gravity within limits.
2. a flash point within limits for ASTM 2D fuel oil,
3. a kinematic viscossty within limits for ASTM 2D fuel oil, l

4.

a water and sediment content within the limits for ASTM 2D fuel oil;

b. Other properties for ASTM 2D fuel oil are within limits within 30 days following sampling and addition of new fuel oil to storage tanks; and
c. Total particulate concentration of the stored fuel oilis < 10 mg/ liter when tested every 31 days tese+en the applicable ASTM Standards #.

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h. Emeroenev Dianal Generator RaliaMW Prooram An emergency diesel generator reliability program that establishes the requirements

' and guidelines for emergency diesel generator reliability, availabihty, and monitoring.

The program snail include the following i

a. Emergency diesel generator reliability performanca goals (target reliability) based 1

upon the station blackout coping assessment. Target reliability goal monitoring is accomplished through monstonng methods that are based upon those descnbod in Appendix D of NUMARC 87-00.

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b. Measures to ensure detailed root cause analysis of emergency diesel generator failures is performed and effective corrective actions are taken in response to failures.
c. Implementation of an emergency diesel generator preventive maintenance program that is consistent with the Maintenance Rule. and i
d. Monitonng of emergency diesel generator availability and performance parameters to ensure the target reliability is met or exceeded

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