ML19308D710
| ML19308D710 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/03/1975 |
| From: | Rodgers J FLORIDA POWER CORP. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003120857 | |
| Download: ML19308D710 (6) | |
Text
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NRU FonM 495 U.S. NUCLEAR REGULATORY c't4MISsloN ooCKET NUMIE R (2 74)
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Mr Schwencer Florida Power Corp
$3-Y-N St Petersburg, Fla J T Rodgers DATE RECEtVED 1-14-77 CLETTER ONoToRIZED PROP (NPUT FORM NUMBER oF COPIES RECE4VEo CoRiciN AL hUNCLASStFIE o brCoPv 1 CC DESCRIPTaoN ENCLoSU RE Ltr trans the following:
Revised pgs to the FSAR proposing that reduced pressure test be removed frem the Ingegrated Leak Rate Test of the
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Reactor Building.......
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Mr. A. Schwencer, Chief ARpiggp ;3 Director of Nuclear Reactor Regulation
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In Re:
Florida Power Corporation Crystal River Unit #3 Docket #50-302
Dear Mr. Schwencer:
Florida Power Corporation feels that te's t results from other utilities have not shown the correlation between Pt (reduced test pressure) and Pa (peak pressure) required to make predictions of leakage rates at Pa, and, there-fore, wish to exclude it from the Reactor Building Inte-grated Leak Rate Test.
Attached are FSAR pages 5 - 7 2',
5-73 and 5-74, which have been revised to remove the reduced pressure test from the Integrated Leak Rate Test.
These revised pages will be included as part of Amendment #48 to the Crystal River
- 3 FSAR.
The FSAR pages in Section 15.0, Technical Specifications, which address containment leakage tests af ter prc-operational tests, were not revised to exclude the reduced pressure test as the entire Section 15.0 will be replaced by the Crystal Piver #3 Standardized Technical Specifica-tions (STS).
The appropriate revisions will be made to the Crystal River #3 STS to exclude the reduced pressure test requirement.
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- ; ^;,x 2-December 3, 1575 Mr. A. Schwencer Should additional discussion be required concerning this proposed revision to the Crystal River #3 FSAR, please do not hesitate to contact this office.
Very truly yours, 1
J.
. Rodger Asst. Vice President JTR/iw Attachments.
4 m
m, (PROPOSED CR #3 FSAR REVISIONS)
Maximum use was made of local pneumatic pressurization during the pre-operational leak monitoring tests to develop methods and procedures for maximu= utilization of this syste= in detecting leakage and locating the leaks. The methods and pro-
- cedures so developed vill thereafter be utilized in detecting and locating leaks throughout the life of the plant.
5.6.3 IHITIAL INTEGRATED LEAK RATE TEST An initial integrated leak rate test was perfor ed in accordance with Appendix J to 10 CFR 50 on the Reactor Building following the cc=pletion of building ccnstruc-tion and the installation of all syste=s penetrating the contain=ent boundarf.
This initial test was performed at the calculated design basis accident pressu e P a
(h9.6 psig). The results of the initial test previded infor=ation for establishing the leakage rate versus pressure characteristics of the building.
The Absolute Pressure-Te=perature Method of =easuring leakage frc= the Reactor Building was employed during the above leakage rate test.
The objectives of the test were:
a.
To verify that the integrated leakage rate does not exceed the design basis accident leakage rate of 0.25 percent by weight of the contained atmosphere in 2h hours.
b.
To obtain a leakage rate histcr/ er.d leakage characteristics of the containment system.
The leakage rate was determined by measuring the leakage frc= the Reactor Building over a period of at least 2h hours after the building te=perature and pressure had stabilized. To ensure equal temperature distribution, fans were provided to circu-late the air in the Reactor Building during the test.
Verification of the leakage rate was cbtained by measuring leakage frc= the Reactor Building while a kncvn leakage rate was superi= posed on the normal building leakage rate.
The difference between the total leakwe and the superi= posed kncvn leakage results is the actual leakage rate.
Thic leakage rate,(difference) vas ec= pared with the original leakage rate as a check against its accuracy.
High-accuracy instru=entation was provided to ensure that the te=perature, pressure, and devpoints of the building at=osphere were accurately measured.
Instrumentation specified for the test consisted of two (2) precision pressure gages, twenty-four (24) resistance temperature detectors and ten (10) dev cells. This provides for adequate instrzentation availability in the event several fail prior to or during the test.
Data frc= these were periodically monitored and recorded throughout the entire integrated leakage rate test.
5-72 J
.~u iPB0 POSED CR'#3 FSAR REVISIONS "
5.6.3.1 Acceptance Criteria
'The maximta allowable leakage rate (La) at ca16ulatrd design basis a.
e accident pressure (Pa) shall not exceed 0.25 percent by weight of contained atmosphere in 24 hcurs.
b.
The initial maximum allowable measured leakage rate *(Lam) at test pressure (Pa) shall not exceed 75 p4rcent of leakage rate L.
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, PROPOSED CR #3 FSAR REVISIONS)~ T 5.6.4 POST OPDATIONAL LEAKAGE RATE TESTS Post operational ~ leakage rate tests are conducted periodically in accordance
' with Appendix J of 10 CFR 50 to ensure that the integrity of containment is maintained and to determine if any leakage problems have developed since the previous inte6 rated leakage rate test.
The post operational leakage rate tests consist of integrated' leakage rate
. tests of the containment system and individual leakage rate. test of canponents which penetrate or seal the boundary of the containment system.
These tests are performed at regular intervals, after major repairs or whenever there is any indication of gross leakage.
5.6.4.1 Jntegrated Leakace Rate Tests (Type A Tests)
These tests are conducted periedically in the same manner as the initial leakage test.
5.6.h.l.1 Acceptance Criteria a.
The measured leakage rate Lam shall not exceed 75 percent of the maxtmun allovable test leakage rate La as established in 5.6.3.1.
b.
In the event L exceeds 0.75 L local leakage repairs shall be as a
made and measured leakage reductions achieved by repair shall be sufficient to make Lam 1 '73 La.
Local leakage repairs vill be reported to the NRC.
c.
In the event Lam exceeds La a report shall be submitted to the NRC for possible revision of the type A test schedule.
5.6.h.l.2 Test Frequency Tests are performed three' times, at approximately evenly spaced intervals during the ten year interval between major in-serivce inspection shutdown.
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