ML18032A694
| ML18032A694 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/14/1988 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18032A695 | List: |
| References | |
| TAC-R00267, TAC-R00268, TAC-R00269, TAC-R267, TAC-R268, TAC-R269, NUDOCS 8801200151 | |
| Download: ML18032A694 (16) | |
Text
1 ACCELERLTED DIAIBUTION DEMONSTRPIION SYSTEM REGULATORY INFORMATION DXSTRXBUTION SYSTEM (RIDS)
ACCESSION NBR: 8801200151 DOC. DATE: 88/01/14 NOTARIZED: YES FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee AUTH.NAME AUTHOR AFFILIATION GRXDLEY,R.
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT Application for amends to Licenses DPR-33,DPR-52
& DPR-68.
Amends revise two incorrect footnote refs.Fee paid.
DISTRXBUTION CODE: A001D COPIES RECEIVED:LTR 3 ENCL 3-SIZE:
TITLE: OR Submittal:
General Distribution NOTES:G.Zech 3 cy.
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 87401 5N 1578 Lookout Place TVA-BFN-TS-237 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of Tenne'ssee Valley Authority Docket Nos.
50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) TVA BFN TECHNICAL SPECIFICATION 237 In accordance with the provisions of 10 CFR 50.4 and 50.90, we are submitting a request.for amendment to licenses DPR-33, DPR-52, and DPR-68 to change the Browns Ferry Nuclear Plant Technical Specifications for units 1, 2, and 3
(enclosure 1).
This proposed amendment will revise two incorrect footnote references:
one in Table 3.2.B, Instrumentation that Initiates or Controls the Core and Containment
- Systems, and one in Table 4.2.K, Radioactive Gaseous Effluent Instrumentation Surveillance.
This amendment has been identified as a restart requirement.
Description, reason for change, and justification in support of the proposed changes are enclosed (enclosure 2).
A proposed determination of no significant hazards consideration is provided in enclosure 3.
Enclosed is a check for the
$ 150 amendment fee required by 10 CFR Part 170.12.
We request that these specifications be made effective 30 days after issuance.
Very truly yours, TE N
SEE V
LEY AUTHORITY Subscrige ~nd sworn
/ ~.
ao before me 1988 R. Gridley, Director Nuclear Li ensing and Regulat ry Affairs Notary Pu lic My Commission Expires Enclosures cc:
See page 2
-gJ-
'8801200151 880114 PDR
,ADOCK 05000259,
.P.....: DCD An Equal Opportunity Employer MMyQO
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U.S. Nuclear Regulatory Commission JAN 14 588 cc (Enclosures):
Hr. K. P. Barr, Acting Assistant Director for Inspection Programs TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission
.Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. G.
G. Zech, Assistant Director For Projects Mail Stop 7E23 TVA Projects Division Office of Special Projects U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland 20814 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant Route 12 P.O.
Box 637
- Athens, Alabama 35611 Hr. Charles R. Christopher
- Chairman, Limestone County Commission P.O.
Box 188
- Athens, Alabama 35611 Dr. C.
E.
Fox State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104 Mr. J.
E. Jones General Electric Company No.
1 Union Square 808 Krystal Building Chattanooga, Tennessee 37402
0
ENCLOSURE 1
PROPOSED TECHNICAL SPECIFICATIONS REVISIONS BRONNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 (TVA BFN TS 237)
S 1
ENCLOSURE 2 DESCRIPTION AND JUSTIFICATION BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 Descri tion of Chan e
The proposed amendment involves two similar changes.
The first change is applicable to BFN units 1
and 2 only. It is to correct a
footnote referenced in Table 3.2.8, Instrumentation that Initiates or Controls the Core and Containment Cooling Systems.
The table entry (page 3.2/4.2-14) for reactor low water level, which in conjunction with other signals will initiate the automatic depressurization system (ADS), is changed to reference note 16 instead of 14.
The second change applies to all three BFN units.
It will delete the reference to footnote 4 in Table 4.2.K, Radioactive Gaseous Effluent Instrumentation Surveillance, for entry number 5 (offgas hydrogen analyzer).
This change effects page 3.2/4.2-62 for units 1
and 2, and page 3.2/4.2-61 for unit 3.
Reason for Chan e
The first change is to correct a footnote referenced in table 3.2.8.
The current footnote referenced for the reactor low water level trip switch which initiates ADS is footnote 14.
This footnote states that a residual heat removal service water (RHRSW) pump would be inoperable.
However, there is no logical connection between this particular switch or its intended function and the RHRSW system.
The footnote to which this roference is being changed is number 16.
This footnote allows one ADS trip
"= system to be out of service for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in order to perform functional testing.
The second change must be made to the entry in table 4.2.K for the offgas hydrogen analyzer since its current footnote (number
- 4) states that there is an automatic isolation signal coming from this instrument;
- however, no such isolation signal exists.
Justification for Chan e
The first change is to correct a footnote reference in table 3.2.8 for the reactor low level trip switch which initiates ADS.
The current note that is referenced. is inappropriate since it states that an RHRSW pump should be declared inoperable, but operation of this switch is not necessary for the RHRSW or EECW systems to perform their safety functions.
The note that will be referenced allows one ADS trip channel to be out of service for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to perform functional testing and calibration.
This note is already referenced for other ADS instrumentation and is currently referenced in the BFN unit 3
Technical Specifications (TS) for this particular instrument channel.
The error was apparently introduced sometime after the TS were reissued on August 20,
- 1976, since this amendment clearly contains the reference to note 16 instead of the current note 14.
No amendment has been found which discusses
1P
Justification for Chan e (Cont'd) changing this note.
- However, amendment numbers 40 and 28 for units 1
and 2
respectively issued on August 2,
- 1978, were particularly illegible at the point where this note is referenced, and may be the source of the error.
For these
- reasons, TVA has determined that this change will correct an error and therefore will not reduce the margin of nuclear safety.
The second change will correct an error in the note referenced for the offgas hydrogen analyzer in table 4.2.K.
The current note (number 4) states that the functional test of the channel will demonstrate that automatic isolation of the offgas line occurs when the channel trips.
However, this instrument channel was not designed to produce an isolation signal.
The Final Safety Analysis Report (FSAR) does not take credi t for or mention an isolation signal coming from the hydrogen analyzers on the offgas system. It only refers to a control room annunciation which does exist for high hydrogen concentrations.
- Also, HUREG 0483, Revision 3, "Standard Radiological Effluent Technical Specifications for Boiling Water Reactor,"
which provides model TS for this table, does not require such an isolation signal.
Furthermore, it would not be an appropriate action to isolate the offgas system on an increasing hydrogen concentration for two reasons.
First, hydrogen is not toxic or radioactive and therefore would not pose any threat to the public if released
- Second, isolating the offgas system with an increasing hydrogen concentration could produce an explosive atmosphere in the condenser or offgas
- system, while continuing to operate the system would dilute and disperse the hydrogen, thereby reducing the possibility of explosion.
For these
- reasons, TVA has determined that this change will correct an error and therefore will not reduce the margin of nuclear safety.
r
%. A 4
h
378" above vessel zero) originating in the core spray system trip system.
The ADS circuitry is capable of accomplishing its protective action with one operable trip system.
Therefore one trip system may be taken out of service for functional testing and calibration for a period not to exceed eight hours.
Two RPT systems exist, either of which will trip both recirculation pumps.
The systems will be individually functionally tested monthly.
If the test period for one RPT system exceeds two consecutive
- hours, the system will be declared inoperable.
If both RPT systems are inoperable or if 1
RPT system is inoperable for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, an orderly power reduction shall be initiated and reactor power shall be less than 85 percent within four hours.