ML20137B549

Forwards Request for Addl Info on 850528 Tech Spec Change Request Re Degraded Grid Voltage Protection for Class 1E Sys.Response Requested within 30 Days of Ltr Receipt

ML20137B549
Person / Time
Site:	Crystal River
Issue date:	12/31/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Wilgus W FLORIDA POWER CORP.
References
NUDOCS 8601150561
Download: ML20137B549 (5)

Text

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if December 31, 1985 a.

D)/\ @ Ob Docket No. 50-302 DISTRIBUTION

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pocket y JPartlow KL ruK Ringram L PDR BMozafari Mr. Walter S. Wilgus PBD-6 Rdg Gray File Vice President, Nuclear Operations FMiraglia RWeller Florida Power Corporatior. OELD EBrach ATTN: Manager, Nuclear Licensing ACRS-10 H0rnstein

& Fuel Management EJordan BGrimes P. O. Box 14042; M.A.C. H-3 St. Petersburg, Florida 33733

SUBJECT:

DEGRADED GRID VOLTAGE PROTECTION FOR THE CLASS 1E SYSTEM-h FERENCES (1)'NRC LETTER OF 8/24/83,(2) FPC LETTER OF 10/19/84, (3) FPC LETTER OF. 5/28/85 #3F0585-19 Region II has completed a review of your responses (References 2 and 3) to the NRC exceptions to an SSER which was issued by Reference 1. We need additional clarification or information before the Technical Specification (TS)

Change Request in Reference 3 can be approved. The additional clarification and/or information needed is discussed in the enclosure.

You are requested to respond to the items discussed in the enclosure within 30 days of receipt of this letter or provide the NRC Project Manager with a response date that you can accommodate. If you have any questions, please contact Project Manager, B. Mozafari at (301) 492-9778.

Sincerely,

• W1GiML #1G:Q 3g

%.?? 83%*/

John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-R

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page Y aae r PBD-6 PBD-6 PB BMozafari;cf RWeller JSto 12/10/85 12/P/85 12/3/85 060115056'1 851231 PDR ADOCK 05000302 P PDR 2

Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant t 1 cc:

Mr. R. W. Neiser State Planning and Development Senior Vice President Clearninghouse and General Counsel Office of Planning and Budget

! Florida Power Corporation Executive Office of the Governor

P. O. Box 14042 The Capitol Building i

St Petersburg, Florida 33733 Tallahassee, Florida 32301

Nuclear Plant Manager Mr. Wilbur Langely, Chairinan i Florida Power Corporation Board of County Commissioners P. O. Box 219 Citrus County .

Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division i Suite 220, 7910 Woodmont Avenue -

Bethesda, Maryland 20814 Resident inspector ,

4 U.S. Nuclear Regulatory Commission '

i Route #3, Box 717 i

Crystal River, Florida 32629 l' Regional Administrator, Revion II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Allan Schubert, Manager Public Health Physicist i Department of Health and

Rehabilitative Services 1323 Winewood Blvd.

Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida '

2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General l Department of Legal Affairs The Capitol -

Tallahassee, Florida 32304 ,

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4 ENCLOSURE

$ ' REQUEST FOR ADDITIONAL INFORMATION DEGRADED GRID VOLTAGE

References:

Enclosures to Florida Power Corporation letters dated 10/19/84 i

f3 F1084-12 (Ref.1) and 5/28/85 #3 F0585-19 (Ref. 2) .

1. Items concerning reference (1)

a.Section II, Specific Requirements, page 1. The first paragraph

, states that no special test points are required for loss of voltage testing; however, the next paragraph and table on page 2 indicate -

[ that TP-2 is a test point for " loss of voltage" testing. There appears to be a conflict, please clarify.

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b.Section II, Specific Requirements, page 1, third paragraph.

" Operation of the TP-3." This phrase is confusing in that tis' are

understood to monitor action rather than initiate the " operation".

This item should be clarified.

c.Section II, Specific Requirements, page 1, third paragraph, second sentence, "undervoltage conditions." Does this refer to action for.

either or both sets of relays, i.e., " Loss of Voltage" and/or i " Degraded Voltage" relays? Both are recognized to sense undervoltage conditions. This paragraph should clearly define the i undervoltage term. In addition, the diesel start signal time i

should be specified and discussed. If the time is different for Loss of Voltage and Degraded Voltage, this should also be discussed.

d. Page 3, circuit breaker designation I

' (1) In addition to circuit breaker numbers, the breakers should  ;

also be identified by description, e.g., breaker 3205, ES "A" j Feeder Breaker from Startup Transformer No. 3.

(2) For ES breakers supplying 5ower to the 480 volt engineered l safeguard busses, does the surveillance testing proposed by i

the Technical Specification affect these breakers, i.e., do they have to be considered for any trip blocking action or  ;

administrative controls during the surveillance test period?

i j 2. Items concerning reference (2) 4

a. Provide reasons and justification for differences between your '

proposed Technical Specification (TS) table 3.3-3, Item 6, table  ;

3.3-5 items 10 and 11, and the B&W Standard Technical Specification {

(STS) [NUREG-0103, Rev 4, 1980].  :

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, b. . Evaluation of request section, first paragraph, "If the undervoltage condition persists for 7 seconds, the ' diesel generator is started." Does the undervoltage condition apply to both relay  ;

protection systems, i.e., " Loss of Voltage" (2 out of 3 logic) and l

" Degraded Voltage" (3 out of 3 logic) -relays? If so, it appears the 2nd sentence with reference to 7.8 seconds is in error. Also see Item 1.c.

c. Evaluation of request section. first paragraph and table 3.3-4, item 6. This implies.and states that the setpoint for loss of' voltage is zero volts. Since Loss of Voltage is a 2 out of 3 logit and Degraded Voltage is 3 out of 3 logic, protection in this area is compromised by a zero volt setpoint. A setpoint.of zero volts for

Loss of Voltage relays is unsatisfactory.

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d. Evaluation of request section, second paragraph, the units designation in parentheses should be " seconds" rather than " volts".

{ e. Table 3.3-4, item 6. Are the time designations under the " Trip 8

Setpoint" and " Allowable Values" columns ccmpatible with NRC's  ;

position given in B&W STS Rev. 4, paragraphs, 4.8.1.1.2.c.4.b) and .

' 4.8.1.1.2.c.7.b) or is a new proposed position on these paragraphs scheduled for inclusion into the STS by a revision? The new proposed revision would be similar to the following:

At least once per 18 months, during shutdown, simulating a

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loss of offsite power by itself, and" i o Verifying de-energization of the emergency busses and '

l load shedding from the emergency busses.

' o Verifying the diesel starts ** on the. auto-start signal, energizes the emergency busses and permanently connected i.

loads within 10 seconds, energizes the auto-connected shutdown 1

E loads through the sequencing times and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization of these loads, the steady state voltage and frequency shall be maintained

at 4160 i 420 volts and 60 1.2 Hz.

i At.least once per 18 months, 'during' shutdown, simulating a loss of power in conjunction with an ESF actuation test signal, and o Verifying de-energization of the emergency busses and load shedding from the emergency busses.

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e o Verifying the diesel starts ** on the auto-start signal, energizas the emergency busses with permanently connected loads within 10 seconds, energizes the auto-connected emergency (accident) loads through the sequencing timers and ooerates for greater than or equal to 5 minutes and maintains the steady

state voltage and frequency at.4160 1 420 volts and 60 1.2 Hz, i

• • This test shall be conducted in accordance with the manufacturer's recommendations regarding engine prelube and warmup procedures, and

as applicable regarding loading recommendations.

$ f. The proposed monthly functional test procedures for these protection systems that have been prepared and approved to implement the TS change 4

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of reference 2 should be provided for review. Also submit any .

i electrical drawing (single line or detailed) plus any other documentation that would aid in the review of the above procedures. ,

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I g. Evaluation of Request, third paragraph. This paragraph concerns the l third item in NRC's letter of August 24, 1983, with regard to the TS change to demonstrate the full-functional operability and independence .

of the onsite power sources at least once every 18 months during 4

shutdown. FPC states that a proposed test for this item was not  ;

, submitted based on their response to Generic Letter (GL) 84-15, Diesel i Generator Reliability.

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! GL 84-15 was generated as a fact finding agent with regard to diesel 1

. generator reliability. The information, as a result of this letter, has

now been evaluated and is to be factored into an NRC positon that will be reflected in a revision to the STS. The Technical Operations Support

Branch, Office of Nuclear Reactor Regulation stated that the STS changes '

should be issued the latter part of this year and that it will be modeled after a North Anna TS change which was issued as a result of GL '

84-15. [For information, the North Anna TS change was issued on April 25, 1985, by a letter from Leon Engles, Operating Reactors Branch #3,

. - Division of Licensing, to W. L. Stewart, Vice President of Nuclear

Operations, Virginia Electric and Power Company and is available in the 4

Public Document Room.]

j This item is still open and is to be resolved by_ the NRC and FPC within i 60 days after FPC's receipt of this B&W STS revision which will be

) issued to confirm NRC's position with regard to GL 84-15. FPC should .

either submit a TS change, provide a schedule for a change, or provide l an exception to this NRC position.

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