ML20196K058

Forwards NRC Position Re Tech Spec Upgrade Program,Per 870825,26,1202 & 03 Meetings.Items Discussed Include Diesel Generator Start Time,Load Tests,Battery Equalizing Charges & Battery Interrack Connection Resistance

ML20196K058
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/07/1988
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Robert Williams PUBLIC SERVICE CO. OF COLORADO
References
TAC-56565, NUDOCS 8803150157
Download: ML20196K058 (7)

Text

r 14 March 7, 1988 Docket No. 50-267 Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado P, O. Box 840 Denver, Colorado 80201-0840

SUBJECT:

TECHNICAL SPECIFICATION UPGRADE PROGRAM (TSUP)

NRC POSITION ON D* ITEMS (TAC NO. 56565)

This letter refers to certain items concerning the TSVP where the NRC staff agreed to provide a plant specific position for Fort St. Vrain (FSV). These items were discussed in our meetings of August 25 and 26, and December 2 and 3, 1987. (Summaries of these meetings are dated October 1, 1987 and January 12, 1988, respectively.) Enclosure 1 to this letter provides the staff's position on these items.

If there are any questions concerning these positions, please contact me at  ;

(301) 492-7000.

t Sincerely,.

NL [

Kenneth L. Heitner, Project Managar  :

Project Directorate - IV

• Division of Reactor Projects - III, IV, V and Special Projects ,

Office of Nuclear Reactor Regu?ation i

Enclosure:

As stated  ;

cc w/ enclosure:  !

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March 7, 1988 Docket No. 50-267 i

Mr. R. O. Williams, Jr.

Vice President, Nuclear Operations Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201-0840

Dear Mr. Williams:

t

SUBJECT:

TECHNICAL SPECIFICATION UPGRADE PROGRAM (TSUP)

NRC POSITION ON D* ITEMS (TAC NO. 56565) z This letter refers to certain items concerning the TSUP where the NRC staff agreed to provide a plant specific position for Fort St. Vrain (FSV). These ,

items were discussed in our meetings of August 25 and 26, and December 2 and 3, 1987. (Summaries of these meetings are dated October 1, 1987 and January 12, 1988, respectively.) Enclosure 1 to this letter provides the staff's position on these items.

If there are any questions concerning these positions, please contact me at i (301) 492-7000.

Sincerely,.

\d,  :

Kenneth L. Heitner, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated l CC w/ enclosure:

1 See next page DISTRIBUTION

' Docket File NRC POR Local POR PO4 Reading DR4A/J. Collins J. Calvo P. Noonan K. Heitner OGC-Bethesda E. Jordan J. Partlow ACRS (10) rD4 Plant File E. Butcher PO4/LA So PD4/PM N N PO4/0 N TS [( g? 1/Ily i PNoonan KHeitner: sr JCalvo)7 E d y/h/

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P Mr. R. O. Williams, Jr.

Public Service Company of Colorado Fort St. Vrain CC:

Mr. D. W. Warembourg, Manager Albert J. Hazle, Director Nuclear Engineering Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 '

Denver, Colorado 80201-0840 '

Mr. David Alberstein, 14/159A Mr. R. O. Williams, Jr. , Acting Manager GA Technologies, Inc. Nuclear Production Division Post Office Box 85608 Public Service Company of Colorado San Diego, California 92138 16805 Weld County Road 19-1/2 -

Platteville, Colorado 80651 Mr. H. L. Brey, Manager Nuclear Licensing and Fuel Division Mr. P. F. Tomlinson, Manager Public Service Company of Colorado Quality Assurance Division i

P. O. Box 840 Public Service Company of Colorado Denver, Colorado 80201-0840 16805 Weld County Road 19-1/2 Platteville, Colorado 80651 Senior Resident Inspector U.S. Nuclear Regulatory Commission Mr. R. F. Walker >

P. O. Box 640 Public Service Company of Colorado Platteville, Colorado 80651 l Post Office Bsx 840 4

Denver, Colorado 80201-0840 Kelley, Stansfield & 0'Donnell Public Service Company Building Cemmitment Control Program Room 900 Coordir.ator 550 15th Street Public Service Company of Colorado Denver, Colorado 80202 2420 W. 26th Ave. Suite 100-0 Denver, Colorado 80211 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission

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611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Chairman, Board of County Commissioners

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of Weld County, Colorado Greeley, Colorado 80631 4

Regional Representative Radiation Programs J Environmental Protection Agency

! 1 Denver Place j 999 18th Street, Suite 1300 Denver, Colorado 80202-2413' i

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FORT ST. VRAIN TECHNICAL SPECIFICATION UPGRADE PROGRAM

. NRC POSITION ON 0* ITEMS PUBLIC SERVICE COMPANY OF COLORADO i 4

2 DOCKET NO. 50-267 The following items have been identified as requiring an NRC position. These items were discussed with the licensee in meetings on August 25 and 26, and December 2 and 3, 1987.

1. Diesel Generator Start Time Surveillance procedure 4.8.1.1.2.e.5.b allows 60 seconds for the diesel generator sets to auto-start and energize the essential buses. '

Surveillance procedure 4.8.1.1.2.f allows 20 seconds to accelerate to 1200 rpm. Section 8.2.5.2 of the upgraded FSAR (Revision 5) states that the diesel generators will pickup load within 15 seconds if offsite power is lost.

1 Discussion PSC stated that the 60 seconds was stated for seismic event considerations, and that the 15 seconds stated in the FSAR was an arbitrary figure. The '

diesel generators were specified at 10 seconds, and current testing shows j that this is achievable. However, there is no time limit that is supported '

by analysis. PSC stated that they are allowed 90 minutes for a loss of  ;

forced circulation. It was noted that there is an air start capacity of 20 seconds in the air start accumulator.

Position I PSC and NRC agreed that 60 seconds was excessive based on lack of air i start capacity. The start test will be considered a failure if the air

, start accumulator is exhausted. PSC will continue'to measure and record actual start times. The NRC will reconsider at a later date if a specific

start time needs to be incorporated into the Technical Specification. The total time limit in surveillance procedure 4.8.1.1.2.e 5.b will be retained, j 2. Diesel Generator Load Tests Surveillance procedures 4.8.1.1.2.b.8 and 4.8.1.1.2.a.7 call for operation

] of the diesel generators at greater than full load capacity. The NRC j suggested, and PSC agreed, that a range of load would be more suitable.

Discussion PSC agreed with the concept, provim:d a footnote allowed transient exclusions (such as when a large actor utarts) outside of the limits.

1 i

PSC proposed on January 11. 1988, a normal load rating of 1150

• 50 KW and an overload rating of 1260 1 60 KW.

Position The staff accepts the PSC proposal.

3. Battery Equalizing Charges Discussion  !

PSC stated that 3 to 4 equa'.. zing charges are needed on each battery annually. The battery disconnected is from its bus for 3 to 5 days during the equalizing charge. The bat.tery is disconnected from the bus to prevent overvoltage damage to powered equipment.

PSC further stated that the present batteries are being replaced. by April 1968 with lead-antimony batteries. With this change, the August 1987 draft technical specifications in the area of battery maintenance may no longer be appitcable.

In discussions with the staff on January 8.1988. PSC stated that the proposeo parameters for the new battery would not require changes to l Table 4.8.2-1. However, the new battery would still require equalizing charges. PSC noted that in an emergency, a battery receiving an equalizing charge could be returned to service. PSC stated that an allowance of two equalizing charges por battery per quarter would be ,

acceptable operationally. These limits would apply in the startup. low power, and power modes only.

i Position The staff accepts the PSC proposal.

4. Battery Inter-rack Connection Resistance Discussion Inter-cell connection resistance has been specified for surveillance except for the inter-rack connection resistance. PSC proposed on .

l January 8. 1988. that it would use a value at 150 microches as per the I Standard Technical Specifications for all connections.

Position The staff accepts the PSC proposal.

l

5. Minimum Battery Voltage Discussion Specification 4.8.2.1.a.2 specified a minimum battery voltage of 121.5 volts. PSC stated that this is based on the minimum cell voltage needed I 1

3-for 56 cells to tors a functional battery of the design duty cycle. PSC i states that this is a carryover from the Standard Technical Specification (4.8.2.1.a.2). In discussions on January 8. 1988. PSC revised the total battery voltage to 120.4 volts. The NRC evaluated this proposal.

n Posi tio_n, The staff finds the current PSC proposal is acceptable.

6. Diesel Fuel Oil Purity Discussion i The monthly testing specified by PSC in Section 4.8.1.1.2.c.2 is stated by the licensee to be functionally equivalent to the tests specified by the Standard Technical Specifications. and is locally available. The licensee indicates that since the auxiliary boilers use the same fuel oil supply, that fuel consumption ranges between 19.000 gallons, per month at l full reactor power operation to 510.000 gallons per month, with J accitional fuel being added more frequently than once per week. Based on i the frequency of fuel oil aedition to that in storage, it appears that monthly testing may not be that timely and beneficial, regardless of the i test procedure used.

j 1

In discussions with the staff on January 13. 1988 PSC proposed the l following approach to assure diesel fuel oil purity in the Technica) l Specifications:

Fuel entering the 10 thousand gallon storage tank would be tested

.' prior to placement in the tank. An imediate "clear and bright" test would be perfomed to deterinine if the fuel is suitable to be )

placed in the tank. Samples woulc be sent for offsite testing of i viscosity and flash point. If the offsite tests were unacceptable.

than aggregate volume samples from the tank would be tested.

1 The tank would also be tested monthly for accumulated water and  !

) particulate matter (to be less than 10 mg/ liter). PSC noted that l

j water was regularly removed from the large supply tanks and diesel engine day tanks. The Technical Specifications would require this l

on a monthly basis. ,

1 The ASTM procedures to be used for the viscosity and flashpoint would l

be specified.

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Additionally, the basis would contain the following points:

- Fuel for the' diesel engines would be controlled by administrative pro-cedures. The primary source for this fuel would be direct delivery.

If fuei from the auxiliary boiler tanks is to be used, it must be shown to be acceptable on the same basis. This requires procedural testing of the auxiliary boiler fuel and regular turnover of the stored fuel.

The basis should also clarify how to proceed if the fuel added to the diesel supply subsequently is found unacceptable, and the maximum time for obtaining test. and retest results.

Position The staff finds the PSC proposal as summarized above acceptable.

7. Seismic Monitorina Instrumentation Surveillance Requirements Table 4.3.2-2 specifies the surveillance requirements for the acceleragraphs and associated seismic triggers.

Discussion The surveillance interval for this type of instrumentation is a compromise between insuring operability without excessive disturbance of the instrument itself.

Position The staff finds that a quarterly check of the instrumentation is sufficient to assure operability. However, the accessible instruments should be visually inspected monthly (with a flashlight).