Text

Amend 71 to License NPF-47,extending Time to Perform Leak Rate Testing of Certain Containment Isolation Valves So That Testing Can Be Performed During Refueling Outage,As Opposed to Requiring Earlier Shutdown to Perform Testing
	ML20063F142
Person / Time
Site:	River Bend
Issue date:	02/02/1994
From:	Adensam E; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20063F130	List: ML20063F128; ML20063F142;
References
	NUDOCS 9402140123
	Download: ML20063F142 (7)
	v • d • e

.

1 gaarco j

?

UNITED STATES

[.

Ef') tj NUCLEAR REGULATORY COMMISSION

-+

j WASHINGTON. D.C. 20566-0001

%..,.s j GULF STATES UTILITIES C0t!PANY**

CAJUN ELECTRIC POWER COOPERATIVE AND ENTERGY OPERATIONS. INC.

DOCKET NO. 50-438 RIVER BEND STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. NPF-47 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Gulf States Utilities

dated November 18, 1993, as supplemented by letters dated December 21, 1993, and January 28, 1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance:

(i)-that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be-inimical to the common defense and security or to the health and safety of the public; and

E01 is authorized to act as agent for Gulf States Utilities Company, which

~

has been authorized to act as agent for Cajun Electric Power Cooperative, and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.

- Gulf States Utilities Company, which owns a 70 percent undivided interest in River Bend, has merged with a wholly owned subsidiary of Entergy Corporation.

Gulf States Utilities Company was the surviving company in the merger.

h 8

P

. E.

The issuance of this amendment is'in accordance with 10 CFR Part 51 of the Commission's regulations and 'all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this' license amendment; 1

and Paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan J

The Technical Specifications contained in Appendix A, as revised 1

through Amendment No. 71 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

E01 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

The license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Elinor

. Adensam, Assistant Director for. gion IV & V Reactors Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

-l

Attachment:

Changes to the Technical Specifications Date of Issuance:

February 2, 1994

r t

ATTACHMENT TO LICENSE AMENDMENT NO.- 71 l

FACILITY OPERATING LICENSE ~NO. NPF-47 DOCKET NO. 50-458

'I Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The overleaf pages are-provided to maintain document completeness.

REMOVE INSERT-3/4 4-12 3/4 4-12 3/4 6-5 3/4 6-5 C

P 2

I J

t l REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

5 gpm UNIDENTIFIED LEAKAGE.

25 gpm total leakage (averaged over any 24-hour period).

c.

d.

0.5 gpm per nominal inch of valve size up to a m:ximum of 5 gpm leakage at a reactor coolant system pressure of 1025 i 15 psig from any reactor coolant system pressure isolation valve specified in i

Table 3.4.3.2-1.

e.

2 gpm UNIDENTIFIED LEAKAGE increase within any period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or less (Applicable in OPERATIONAL CONDITION 1 only).

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With any PRESSURE BDUNDARY LEAKAGE, be in at least HOT SHUTDOWN within a.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With cqy reactor :oolant system leakage greater than the limits in b

'I and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

With any reactor coolant system pressure isolation valve leakage greater c.

than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two other closed manual, deactivated automatic or check

valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN witnin the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

d.

With one or more of the high/ low pressure interface valve leakage pressure monitors shown in Table 3.4.3.2-2 inoperable,-restore the inoperable monitor (s) to b?ERABLE status within 7 days or verify the-pressure to be less than the alara point at least'once per 12-hours;-

restore the inoperable monitor (s) to OPERABLE status within 30 days i

or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The provisions of Specifi-cation 3.0.4 are not applicable.

l With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater e.

than the limits in e., above, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months identify the source of leakage as not IGSCC susceptible material or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Which have been verified not to exceed the allowable leakage limit at the last refueling outage or after the last time the valve was disturbed, whichever is more recent.

I J

RIVER BEND - UNIT 1 3/4 4-11 Amendment No. 57

^

t REACTOR COOLANT SYSTEM SURVEILLANCE RE0VIREMENTS-4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be within each of the above limits by:

a.

Monitoring the drywell atmospheric particulate radioactivity at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

Monitoring the sump flow rates at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , c.

Monitoring the drywell air coolers condensate flow rate at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and d.

Monitoring' the reactor vessel head flange leak detection system-at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be. demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 including paragraph IWV-3427(B) of the ASME Code and the -

RBS Inservice Test Program and verifying the leakage of'each valve to be within

'l the specified limit.

i The provisions of Specification 4.0.4 are not applicable for entry.into OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valve leakage pressure monitors shall be demonstrated OPERABLE with alarm setpoints per Table 3.4.3.2-2 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and i

b.

CHANNEL CALIBRATION at least once per 18 months.

f i

RIVER BEND - UNIT 1 3/4 4-12 Amendment No. 7,67, 71 f

l

~

CONTAINMENT SYSTEMS-f SURVEILLANCE RE0VIREMENTS (Continued) b.

If any periodic Type A test fails to meet 0.75 La, the test schedule

~

for subsequent Type A tests shall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet 0.75 La', a Type A test shall be performed at least every 18 months until.two consecutive Type A tests meet 0.75 La, at which time the above test schedule may be resumed.

c.

The accuracy of each Type A test shall be verified by a supplemental test which:

1.

Confirms the accuracy of the test by verifying that the l

difference between the supplemental test data and the Type A test data is within 0.25 La. The formula to be used is:

[Lo + Lam - 0.25 La] s Lc s (Lo + Lam + 0.25 La) where Lc -

i supplemental test results; Lo - superimposed leakage; Lam =

i measured Type A leakage.

2.

Has duration sufficient to establish accurately.the ehange in leakage rate between the Type A test and the supplemental test.

3.

Requires the quantity of gas, injected into the primary containment or bled from the primary containment during the supplemental test, to be between 0.75 La and 1.25' La.

d.

Type B and C tests shall be conducted with gas at Pa, 7.6 psig*, at intervals no greater than 24 months ** except for tests involving:

1.

Air locks,

~

2.

Main steam positive leakage control system (MS-PLCS) valves and PVLCS valves, 3.

Penetrations using continuous leakage monitoring systems, 4.

Primary containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment, and 5.

Purge supply and exhaust isolation valves with resilient material seals.

e.

Air locks shall be tested ami demonstrated OPERABLE per Surveillance Requirement 4.6.1.4.

f.

Total sealing at leakage into the primary containment, at a test pressure of 11.5 psid for.MS-PLCS valves and 33 psid for penetration leakage control system sealed valves, shall be determined by. test at least once per 18 months **. This leakage may be excluded when determining the combined leakage rate, 0.6 La.

~

Unless a hydrostatic test is required per Table 3.6.4-1.

- A one-time schedular extension has been granted to a.llow this test to be performed during the refueling outage following the fifth cycle, scheduled to begin April 16, 1994.

RIVER BEND UNIT 1 3/4 6-5 Amendment' No. 7,71

f CONTAINMENT SYSTEMS

~

SURVEILLANCE REQUIREMENTS (Continued)

I g.

Type'B tests for electrical penetrations employing a continuous leakage l

monitoring system shall be conducted at Pa, 7.6 psig, at intervals no

- l greater than once per 3 years.

h.

Leakage from isolation valves that are sealed with the PVLCS shall be tested once per. 24 months with the valves pressurized to at least Pa, 7.6 psig. This leakage may be excluded when detenmining the combined leakage rate 0.6 La.

t 1.

Primary containment isolation valves in hydrostatically tested lines per Table 3.6.4-1 which penetrate the primary containment shall be leak tested at least once per 18 months *.

l J.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.9.3.

k.

The provisions of Specification 4.0.2 are not applicable.to Specifications 4.6.1.3.a. 4.8.1.3.d. 4.6.1.3.g and 4.6.1.3.u.

s C

This test may be performed during the refueling outage following the first cycle, scheduled to begin September 15, 1937.

RIVER BEND - UNIT 1 3/4 6-6 Amendment ik). 7 l

l

.

ML20063F142

Text

Attachment:

Navigation menu

Search