ML19259A753
| ML19259A753 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/04/1979 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901100262 | |
| Download: ML19259A753 (4) | |
Text
.
TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ol 500C Chestnut Street Tower II J AM 04 N s
Director of Nuclear Reactor Regulation Attention:
Mr. Thomas A. Ippolito, Chief Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Ippolito:
In the Matter of the
)
Docket No. 50-296 Tennessee Valley Authority
) of the May 25, 1977, letter from me to Edson G. Case was submitted as a portion of the E w r Ferry unit 3 inservice inspection and testing program.
It has since been discovered that a technical specification surveillance requirement had been inadvertently omitted from two pages. To amend this editorial error we are resubmitting as an enclosure hereto the two pages from the unit 3 technical specifications which have the corrections indicated.
Very truly yours, J. E. Gilleland Assistant Manager of Power Enclosures 79011002G 2 An Equal Opportunity Employer
e 3
0 m
e ENCLOSURE
4 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE RFQUIREMENTS O
J.S CO_Rg AND COPCAINMENT 84.5 CORE AND COtRAINNEPC COOLING
^
COOLING SYSTEMS SYSTEMS s
E.
High Pressure Coolant E.
Hi_gh Pressure Coolant Iniection System (HPCIS)
Iniection System (HPCI S) 1.
The HPCI system shall 1.
HPCI Subsystem be operable:
testing shall be performed as follows:
( 1) prior to startup from a Cold a.
Simulated Once/
Condition; or Automatic operating Actuation cycle (2) whenever there Test is irradiated fuel in the b.
Flow rate Once/
reactor vessel and the reactor at 150 psig operating vessel pressure cycle c.
9' Inservice testing of ASME Code Class 1, 2p ex ept Class 2, and Class 3 pumps and valves as specified in
^
specification shall ';e performed in accordance with 3.5.E.2.
Secti'an XI of the ASME Boiler and Pressurt Vessel Code and applicable 2.
If the HPCI system in Addenda as required by 10 CFR 50, Section inoperable, the 50.55a(g), except where specific written reactor may remain in relief has been granted by the NRC 6
operation for a pursuant to 10 CFR 50, period not to exceed Section 50.55a(g)(6)(1).
7 days, provided the ADS, CSS, RHRS (LPCI), and RCICS are The HPCI pump shall operable.
deliver at least 5000 gpm during each flow 3.
If specifications rate test.
3.5.E.1 or 3.5.E.2 are not met, an 2.
When it i. determined orderly shutdown that the l'PCIS is shall be initiated inoperable the ADS and the reactor actuation logic, the vessle pressure shall RCICS, the RHRS be reduced to 122
( LPCI), and the CSS psig or less within shall be demonstrated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
to be operable immediately:
The RCICS and ADS logic
^
shall be demonstrated to be operable daily q
thereafter.
159
t LIMITING CONDITIONS FOR OPEPATION SURVEILLANCE REQUIREMENTS v
l. 'e COKE AND CONTAINMENT
- 4. 5 CORE _AND CONTAINMEtTP COOLING CUUL5UG~3YSTEMS SYSTEMS F.
Reactor Core Isolation Cooling System ( RCI CS)
F.
Reactor Core Isolition Cooling System (RC ICS) 1.
The RCICS shall be 1.
RCIC Subsystem operable:
testing shall be performed as follows:
(1)
Prior to startup from a Cold a.
Simulated Once/
Condition; or Automatic operating Actuation cycle (2) whenever there Test is irradiated fuel in the b.
Flow rate Once/
rea r vessel at 150 psig operating and the reactor vessel pressure c.
1sao
- g Inservice testing of ASME Code Class 1, pg q e cep as v
specified in Class 2, and Class 3 pumps and valves 3.5.F.2.
shall be performed in accordance with s_
Section XI of the ASME Boiler and 2.
If the RCICS is Pressure Vessel Code and applicable inoperable, the Addenda as required by 10 CFR 50, reactor nay remain in Section 50. 75a(g), except where operation for a specific written relief has been pejfd granted by the NRC pursuant to ot t he
- PC S is operable during 10 CFR 50, Section 50.55a(g)(6)(i).
such time.
3.
If specifacations The RCIC pump shall 3.5.F.1 or 3.5.F.2 deliver at least 600 gpm during each flow are not met, an orderly shutdown test.
shall be initiated and the reactor shall 2.
When it is determined be depressurized to that the RCICS is less than 105 psig in perable, the HPCIS within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
shall be demonstrated to be operable immediately and weekly thereafter, t
%/
s-160
_..