ML20009E300
| ML20009E300 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/15/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Carey J DUQUESNE LIGHT CO. |
| Shared Package | |
| ML20009E301 | List: |
| References | |
| TAC-44830, NUDOCS 8107280019 | |
| Download: ML20009E300 (5) | |
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Mr. J. J. Carey, Vice President IE-3 Nuclear Division 7
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Duquesne Light Company AE0D Post Office Box 4
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Dear Hr. Carey:
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Our letter dated April 29,1981 infomed you that the containment Nrge and vent requirements for Beaver Valley Power Station, Unit No.1 had been satisfied with the possible exception of changes to Technical Speci-fications (TS) that might be detemined to be necessary as a result of the continuing long-term myiew by the staff.
The staff has completed their review and concluded that the purge and vent system design and operating practices for Beaver Valley Power Station, Unit 1 are acceptable. However, as a result of the numerous reports on unsatisfactory performance of the resilient seats for butterfly-type iso-lation valves in containment purge and vent lines, periodic leakage integ-rity tests of the above 42-inch and 8-irich butterfly isolation valves have been found necessary. We, therefore, require that the licensee propose a technical specification for testing these valves in accordance with the following recommended testing frequency:
"The leakage integrity tests of the isolation valves in the con-tainment purge lines and the stean jet air efector systen lines shall be conducted at intervals 60t to exceed 6 months.Y The purpose of the leakage integrity tests of the isolation valves in the i
containment purge lines and the steam jet air ejector system lines is to identify excessive degradation of the resilient seats for these valves.
Therefore, they need not be conducted with the pmcision required for the Type C isolation valve tests in 10 CFR Part 50, Appendix J.
These tests would be performed in addition to the quantitative Type C tests requimd l
by Appendix J and would not relieve the licensee of the responsibility to conform to the requirenents of Appendix J.
Further clarification of these requirements is given in Enclosum (1).
These changes to your TS, in conjunction with previous actions taken l
at your facility, will satisfy the staff concerns, with the exception of i
Positi6ns 5, G, and 7 of NUREG-0737 Item II.E.4.2, regarding containment purge and vent at Beaver Valley Power Station, Unit No.1. He mquest that your propose a TS change incorporating the test requirements together 8107280019 01071S DR ADOCK 0S000 OFhCEb sonnuc >
om) une ronu m 0o-803 nacu em OFFICIAL RECORD COPY usam e-m a
a N.J.J.Carey
' Mith the details of your proposed test program within 45 days of re-cefbt of this letter.
A copy of our Safety Evaluation Report is enclosed for your infomation.
If you have any questions or concerns, please feel free to contact us.
Sincerely, Original 316ned by 8 S.A.Varga Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
Enclosures:
1.
Purge / Vent Valve Leakage Tests 2.
Safety Evaluation Report cc: w/ enclosures See next page
- Previous concurrence see next naqe o,nce>..oggi;pL *,.
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Mr. J. J. Carey
.Duanesne Light Company cc:
Mr. R. J. Washabaugh, QA Manager Gerald Charnoff, Esquire Duquesne Light Company Jay E. Silberg, Esquire Quality Assurance Department Shaw, Pittman, Potts and Trowbridge Post Office Box 4 1300 M Street, N. W.
Shippingport, Pennsylvania 15077 Washington, D. C.
20036 Mr. J. A. Werling Karin Carter, Esquire Station Superintendent Special Assistant Attorney General Duquesne Light Company Bureau of Administrative Enforcement Seaver '/ alley Power Station 5th Floor, Executive House Post Office Box 4
.Harrisburg, Pennsylvania 17120 Shipoingport, Pennsylvania 15077 Mr. Roger Tappan Mr. T. O. Jones, Manager Stone & Webster Engineering Corporation Nuclear Operations P. O. Box 2325 Duquosne Light Company Boston, Massachusetts 0210/
Post Office Box 4 Shippingport, Pennsylvania 15077 Mr. F. Noon R & D Center Mr. F. J. 31ssert, Manager Westinghouse Electric Corporation Nuclear Support Services Suilding 7-303 Duquesne Light Company Pittsburgh, Pennsylvania 15230 Nuclear Division Post Office Box a Marvin Fein Shippingport, Pennsylvania 15077 Utility Counsel City of Pittsburgh Mr. R. M. Mafrice, Nuclear Engineer 313 City-County Building Cuquesne Light Company Pittsburgh, Pennsylvania 15219 435 Sixth Avenue Pittsburgh, Pennsylvania 15213 Mr. John A. Levin I
Public Utility Ccemission Mr. R. E. Martin, Nuclear Engineer
?. O. Box 3255 Cuquesne Light Company Harrisburg, Penn~ jlvania 17120 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Irwin A. Popowsky, Esquire Office of Consumer Advocate Mr. N. R. Tonet, Manager la25 Strawberry Square Nuclear Engineering Farrisburg, Pennsylvania 17120 Juquesne Light Company Nuclear Di"ision Charles E. Thomas, Esquire Post Office Sox a Thomas and Thomas Shippirg; ort, Pennsylvania 15077 212 Lccust Stree:
Sox 999 "r. J. D. S i e be r, Ma na g e r Harriscurg, Pennsylvania 17103 Nuclear Safety & Licensing Cuquesna Light Company Resident Inspector Nuclear Civision U. S. Nuclear Regulatory Commission Post Office Sox 1 Post Office Sox 293 Shipping;cet, Pernsylvania 15077 Shippingport, Pennsylvania 15C77 i
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PURGE / VENT VALVE LEAKAGE TESTS The long term resolution of Generic Issue 3-2t, " Containment Purging During Hermal Plant Operatien," includes, in part, the implementation of Item 3.4 specifies Item 3.4 of 3 ranch *echnical Position (377) CSB 6 4
- hat provisions shculd be made for leakage rate testing of the (purge / vent 4
Although system) isciation valves, individu't11y, during reactor operation.
50 specifies a maximum test interval of 2 years.
As a result of the numerous reports Jon unsatisfactory performance of %e resfif ent seats for the isolation valves in containment purge and vant lines (addressed in OIE CircJlar 77-ll, dated September 6,1977), Gene,ic Issue 3-20 " Containment Leakage Due to Seal Deterioration," was established to evaluate the' matter and establish an appropriate testing frequency for the Excessive leakage past the resilient seats of isolation isolation valves.
valves in purge / vent lines is typically caused by severe environmental con-Consecuently, the leakage test.
ditions and/cr wear due to frequent use.
frecuency for these valves should be keyed.to the occurrence of svers environ-mental conditions and the use of ne valves, rather than the current require-4 ments of 10 CFR 50, Appendix J.
It is rec mmended nat the folicwing provision be added to the Technical 4
3pecif 4:ations #:r the leak testing of purge /ven line isolation valves:
" Leakage in agrity tests shall be performed on the containment isolation valves si n resilient material seals in (3) active purge /vant systems (i.e., those whicn may be acerated during clant c: era-ing Modes 1 through ) 3: leas; ance every three mon ns 1. c (c) passive surge systems (i.e., : nose wnich must be administratively :0ntr:11ed closed during reac:Or 0;erating
'4cdes 1 througn 4) at leas: Once every six mon:hs."
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-he above proposed surveillance specification is
.1an ic e*cn de By way {te,,,. 0' r $xpa. -- 35'icn tha a plant would have a need to go to cold predica
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2 It is intended that the acove pecposed surveillance specification be aoplied 1.e., the to the active purce/ vent lines, as well as passive purge lines:
purge lines that are administratively controlled closed during reactor oper-The reason for including the cassive Ourge lines is that ating modes 1-4 3-20 is concerned wtih the potential adverse effect of seasonal weatner con-Consequently, passi te ditions on the integrity of the isolatien valves.
purge lines must also be included in the surveillance prog *1m.
4.itegrity tests of the isolation valves in the The purpose of the leakage containment purge and vent lines is to identify excessive degradation of the resilient seats for these valves. Therefore, tney need not be conducted with the orecision required for the Type C isolation valve tests in 10 CFR These tests would be performed in addition to the Part 50, Aopendix J.
uantitative Type C tests required by Aopendix J and -ould not relieve -he licensee cf the responsibility to ccaform o the recuirements of Apoendix J.
In view of the wide variety of valve types and seating materiais, the acceptance criteria for such tests should be developed on a plant-specific casts.
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