ML19296B794

Tech Spec Change Request 60 for Amend to OL App A.Consists of Replacement Pages 3/4 6-20 & 3/4 6-21 Implementing Improved post-accident Containment Atmosphere Sampling Capability Required by NUREG-0578,Item 2.1.8.a

ML19296B794
Person / Time
Site:	Crystal River
Issue date:	02/14/1980
From:	FLORIDA POWER CORP.
To:
Shared Package
ML19296B789	List: ML19296B788 ML19296B794
References
RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8002210509
Download: ML19296B794 (3)

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Director Page Two February 14, 1980 A licensing fee is not applicable to this Change Request as it is the result of an NRC requirement. A signed copy of Certificate of Service for Technical Specification Change Request No. 60 to the Chief Executive of Citrus Country, Florida, is enclosed.

Very truly yours, FL) POWER ORPORATION w '

J A. Hancock

( irector Nuclear Operations JAHhe4104(D1)

Enclosures cc: Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Suite 3100 101 Marietta Street Atlanta, GA 30303 80022.1o Q

STATE OF FLORIDA COUNTY OF PINELLAS J. A. Hancock states that he is the Director, Nuclear Operations, of Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.

as. A. Hancock Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 14th day of February,1980.

b Notary Public Notary Public, State of Florida at Large, My Commission Expires: August 8, 1983 CameronNotary 3(D12)

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF )

) DOCKET NO. 50-302 FLCRIDA POWER CORPORATION )

CERTIFICATE OF SERVICE J. A. Hancock deposes and says that the following has been served on the Chief Executive of Citrus County, Florida by deposit in the United States mail, addressed as follows:

Chairman Board of County Commissioners of Citrus County Citrus County Courthouse Inverness, Florida 32650 One (1) original copy of Technical Specification Change Request No. 60, requesting amendment to Appendix A of Operating License No. DPR-72.

FLORIDA POWER CORPORATION

$) W' -

,df.A.Hancock Virector, Nuclear Operations SWORN TO AND SUBSCRIBED BEFORE ME THIS 14th DAY OF FEBRUARY,1980.

Y-

' Notary Public Notary Public State of Florida at Large My Commission expires: August 8, 1983 (NOTARIAL SEAL)

(CameronCert. Serv.012)

TECHNICAL SPECIFICATION CHANGE REQUEST NO. 60 (APPENDIX A)

Delete pages 3/4 6-20 and 3/4 6-21 with the attached revised pages 3/4 6-20 and 3/4 6-21.

Proposed Change In Table 3.6.1, Section C, Item 2: add LRV-46 as the last valve, included in the isolation of the Leakage Rate test panel from the Reactor Building.

In Table 3.6.1, Section C, Item 5: add SAV-23 & 122 as valves that also isolate the Station Air from the Reactor Building.

In Table 3.6-1, Section D: delete Blind Flange 116.

Reason for the Proposed Change On January 2, 1980, Florida Power Corporation received an Order from the Commission to implement the Lessons Learned (NUREG-0578) unless otherwise exempted. This modification partially implements Item 2.1.8.a, Improved Post-Accident Sampling Capability of that NUREG. A containment atmosphere sample will be able to be drawn by a jet pump through the Leakage Rate test panel and exhausted back to the containment by a connection to the Station Air System.

Safety Analysis of Proposed Change The boundary of the containment, as it goes through a penetration, ends at the outside of the second isolation device. At the present time, these two penetrations have one isolation device inside containment and one outside containment. This Proposed Change will allow Crystal River - Unit 3 to use two isolation devices outside of containment to fulfill the double isola-tion function of each penetration, while at the same time, allowing the opening of the inside containment isolation device. Thus, the boundary of the containment will be extended to the outside of the second isolation device outside of contai nment . Containment atmosphere sampling (post-accident or otherwise) could then be accomplished from outside containment without the need for making a containment entry.

This Proposed Change does not diminish any of the requirements applicable to the Safety Analysis and no unreviewed safety question is involved. It does, however, allow for the implementation of the modification to permit post-accident containment atmosphere sampling at Crystal River - Unit 3 as required by item 2.1.8.a of NUREG-0578, Short-Term Lessons Learned Reconmendations.

TSCRN60(D89)

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (seconds)

10. WDV-4 iso. WDT-4 from RB sump 60 WDV-3 60 WDV-60 & 61 iso. WDT-4 from WDT-5 60 WDV-94 & 62 iso. WDT-4 from WDP-8 60 -

WDV-406 iso. gas waste disposal 60 WDV-405 from vents in RC system 60

12. WSV-3 iso. containment monitoring 60 WSV-4 system from RB 60 WSV-5 60 WSV-6 60 B. CONTAINMENT PURGE AND E)HAUST

1. AHV-1C & ID iso. pur. sup. system 60 AHV-1B & 1A iso. pur. exhaust system 60 C. MAhUAL

1. IAV-28 iso. IA from RB NA IAV-29 NA

2. LRV-50 iso leak rate test system NA LRV-36 from RB NA LRV-51 iso, atmos. vent and RB NA LRV-35 & 47 purge exhaust system from RB NA LRV-49 iso. atmos vent from RB NA LRV-38 & 52 NA LRV-45 iso. LR test panel from RB NA LRV-44 NA LRV-46 NA

3. MSV-146# iso. NG system from NA tank from RCSG-1B

4. NGV-62 iso. NG system from NA NGV-82 # steam generators NA NGV-82 iso. NG system from pzr. NA CRYSTAL RIVER - UNIT 3 3/4 6-20

TABLE 3.6-1 (Continued)

CONTAINMENT ISOLATION VALVES VALVE NUMBER FUNCTION ISOLATION TIME (seconds)

5. SAV-24 iso. SA from RB NA SAV-23 & 122 NA

6. SFV-18 iso. SF system NA SFV-19 NA SFV-119 # iso. Fuel Transfer tubes NA SFV-120 # f rom F.T. Canal NA

7. WSV-1 containment monitoring NA WSV-2 system from RB NA D. PENETRATIONS REQUIRING TYPE B TESTS Blind Flange 119 iso. RB NA Blind Flange 120 NA Blind Flange 202 NA Blind Flange 348 iso. fuel transfer tube from NA Blind Flange 436 Transfer Canal NA Equipment Hatch iso. RB NA Personnel Hatch iso. RB NA

1. Not subject to Type C Leakage Test

• • The provisions of Specification 3.0.4 are not applicable until startup for Cycle 3 operation. Isolation valves closed to satisfy the requirements of Specification 3.6.3.1 ACTION b. and c. may be re-opened on an intermittent basis under administrative control for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in any 24-hour period as necessary for sampling.

CRYSTAL RIVER - UNIT 3 3/4 6-21