ML18142B949
| ML18142B949 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/28/1977 |
| From: | LeBoeuf, Lamb, Leiby & MacRae, Rochester Gas & Electric Corp |
| To: | Case E Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18142B949 (23) | |
Text
DISTRIBUTION AFTER ISSUANCE OF OPERATQfG LZCEVLSE NRCPOAM 19S VA NUCLSAR ASGULATORYCOMMISSIO IZ-Tgl o~
NRC DISTRlBUTlON PGR PART 50 DOCKET MATERlAl.
COOLEST NUMSSR PII,S NUMSSA
! TO:
Mr. Edson Go Case FROM:
- LeBoeuf, Lamb, Leiby & MacRae Washington, D
C.
- Leboeuf, Lamb Leiby & MacRae OATS OP OOCVMSNT 11/28/77 C4LTS RSCSIVSO ill 29 77
~TTSR
~ORIGINAL SCOPY G NOTO AIXS0
~VNCLASSIPISO PROP INPUT POAM NVMSSR OP COPISS ASCSIVSO
'. CSSCAIPTION I
I I
l~
SNCLOSV AS License No DPR-18 Appl for Amend: tech specs proposed chanse-concerning request for modification of reporting requirements and request for modification of tech spec tabi;e 3 '3-1 to add a shock suppressor to the list of safety related shock suppressors.
~ ~ ~ ~
notorized 11/18/77 '
~ w/att Cert of Svc
~ ~ ~
I I PLANT Vu(E: Ri E ~ Ginna Unit No+
1 RJL 11/>0/77 (1-P)
(2-P)+(9-P)
SAFETY Smycv CHZEF:
(T)
FOR ACT lON/lNFORMATION REG FXL
~<TR~R I Q E (2)
INTcRNAl 0 R(SUTlON HANAUER CHECK
~ER&
".ZSLVHT SHAO SUTLER 0
LPDR:
&TERNALOISTR(8UTlGN CONTROI. iVUMBfR VS C
16 CYS ACRS SENT CA~
I'UI03%IIIiKG'llIIIIII LEBOEUFI LAMB,LEIBY ec MACRAE I757 N STREET, N.W.
WAsHINGTQN,D. C. 20036 TELEPHONE 202 e67 7600 CASLE ADDRESS RANDALLJ. LaBDEVF,JR. I929 I976 ADRIAN C. LEIBY I962 I976 LEON A. ALLEN.JR.
JOSEPH C.BACHELDCR.IIE ERNEST S. BALLARD.JR.
G. S. PETER BCROEN a OEOFFRY D.C.BCST DAVID P. DICKS TAYLOR R. BRIGGS CHARLES N. BURGER THOMAS C.BURKE ROGER D.FCLDMANee EVOENC R. FIDELLa a JACOB FRIEDLANDER DONALD J.GREENE JAMEs A.GREERo11a JoHN I.. OROSE a DOUGLAS W HAWKS CARL D.HOBELMAN MICHAEL IOVCNKO JAMES F. JOHNSON, AYw RONALD D.JONES LEX K.LARSON+a ORANT S.LEWIS CAMERON F. MACRAE a CAMERON F. MACRAC 111 a OCRARD A.MAHCR SHCILA H. MARSHALL JAMCS G. Mc E LROY JAMES P. MCGRANCRY,JR ea PHILIP PALMER MCOVIOAN JAMES O'ALLEY,JR.a J ~ MICHAEL PARISH JOHN A.RVDY PAUL G.RUSSELL HAROLD M. SEIDEL CHARLES Pi SIFTON HALCYON O. SKINNER JOSEPH S.STRAUSS SAMUEL M.SUDDEN EUGENE B. THOMAS'R ea LEONARD M. TROSTEN+ S HARRY H. VOIOT' a
H RICHARD WACHTEL OERARD P. WATSON 1
LESWIN,WASHINGTON,D, C, TELEX: ee027e OF COVNSCL ARVIN C. UPTON Iso BROADWAY NEW YORK, N ~ Y. 10006 TELKPNDNL 2I2 269 II00 CABLE ADDRESS LCBWIN,NEW YORK TELEX: 423eIS November 28, 1977 n
n
+RCSIDCNT PARTNERS WASHINGTON OFFICE S ADMITTED TO THC DISTRICT OF COLUMBIA BAR Mr. Edson G.
Case V gX/
Acting Director
',',,l 'c'~',. 6 p
Office of Nuclear Reactor
"~ 'OP+
fP Regulation U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Re:
Rochester Gas and Electri tion R. E. Ginna Nuclear Power Station, Unit No.
1 Docket No.
50-24'4'ear Mr. Case:
As counsel for Rochester Gas and Electric Corpora-
- tion, we hereby transmit three (3) signed originals and nineteen (19) copies of a document entitled, "Application for Amendment to Operating License," together with forty (40) copies of proposed changes to Technical Specifications and accompanying safety evaluation.
This Application seeks to amend Technical Specification 6.9 set forth in Appendix A to Provisional Operating License No. DPR-18, by modifying the requirements for reporting information to the Commission and to modify Technical Specification Table 3.13-1 by adding a
shock suppressor to the list of safety related shock suppres-sors
~
A Certificate of Service showing service of these documents upon the persons listed therein is also enclosed.
Enclosures
BEFORE THE UNITED STATES NUCLEAR REGULATORY COMMISSION In the Matter of ROCHESTER GAS AND ELECTRIC CORPORATION (R. E. Ginna Nuclear Power Station, Unit No.
1)
)
)
)
Docket No. 50-244
)
)
)
CERTIFICATE OF SERVICE I hereby certify that I have served a
document entitled, "Application for Amendment to Operating License" together with a copy of the proposed changes to Technical Specifications and accompanying safety evaluation by mailing copies thereof first. class, postage prepaid to each of the following persons this 28th day of November, 1977:
- Chairman, Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Atomic Safety and Licensing Appeal Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. Michael L. Slade 1250 Crown Point Drive
- Webster, New York 14580 Warren B.
Rosenbaum, Esp.
One Main Street East 707 Wilder Building Rochester, New York 14614 L.
Dow Davis, IV, Esp.
Office of the Executive Legal Director U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Edward Luton, Esq.
Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr.
Emmeth A. Luebke Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dr. A. Dixon Callihan Union Carbide Corporation P.
O.
Box Y Oak Ridge, Tennessee 37830 Mr. Robert N. Pinkney Supervisor Town of Ontario 107 Ridge Road West
- Ontario, New York 14519 Jeffrey L. Cohen, Esq.
New York State Energy Office Swan Street Building Core I, Second Floor Empire State Plaza
- Albany, New York 12223 Lex K. Larson
- LeBoeuf, Lamb; Leiby 6 MacRae Attorneys for Rochester Gas and Electric Corporation
~
I
<ol L
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Rochester Gas and Electric Corporation (R.E. Ginna Nuclear Power Plant, Unit No.
1)
)
)
)
Docket No. 50-244
)
)
APPLICATION FOR AMENDMENT TO OPERATING LICENSE Pursuant to Section 50.90 of the regulations of the U.S.
Nuclear Regulatory Commission (the "Commission" ), Rochester Gas and Electric Corporation
("RG&E"), holder of Provisional Operating License No. DPR-18, hereby requests that the Technical Specification 6.9 set forth in Appendix A to that license be amended to modify the requirements for reporting of information to the Commission.
This request for a change in the Technical Specifications is submitted in accordance with a letter from A. Schwencer, Chief, Operating Reactors Branch 51, dated September 16, 1977.
Additionally, a change is requested in Technical Specification Table 3.13-1 to add a shock suppressor to the list of safety related shock suppressors.
The proposed technical specification change is set forth in Attachment, A to this Application.
A safety evaluation is set forth in Attachment B.
This evaluation also demonstrates that the proposed change does not involve a significant change in the types or a significant increase in the amounts of effluents or any change in the authorized power level of the facility.
I*
WHEREFORE, Applicant respectfully requests that Appendix A to Provisional Operating License No. DPR-18 be amended in the form attached hereto as Attachment A.
Rochester Gas and Electric Corporation L.D. White, Jr.
Vice President, Electric and Steam Production Subscribed and sworn to before me on this Jj 5ay of November 1977.
SHARON G. CAVALER(
NOTARY PUBLIC, State of N.Y.~ Monroe Coun'Ay Commission Expires March 30, 19+/
'1 P
Attachment A
l.
Replace pages 6.9-1, 6.9-2, 6.9-3 and 6.9-10 with the enclosed revised pages 6.9-1, 6.9-2, 6.9-3, and 6.9-10.
2.
Replace page 3.13-.4 with enclosed revised page 3.13-4.
"I lf l II E
6.9 Re ortin Re uirements In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Director of the appropriate Regional Office of Inspection and Enforcement unless otherwise noted.
6.9.1 Routine Reports a
~
Startup Report.
A summary report. of plant startup and power escalation testing shall be submitted following (1)'receipt of an operating license, (2) amendment to the license involving a planned increase in power
- level, (3) installation of fuel that has a different design or has been manufactured by a different fuel
- supplier, and (4) modifications, that may have signifi-cantly altered the nuclear, thermal, or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.
b.
Startup reports shall be submitted within (1) 90 days following.completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e, initial criticality, completion of startup test program, and resumption or, commencement of commercial power operation),
supplementary reports shall be submitted at least every.three months until all three events have been completed.
Mo'n'th'1 Opera't'in'e 'o'r't.'outine reports of operating statgstxcs and shutdown experience shall be submitted on a monthly basis to the Director, Office of Management Information and Program Control, U.S. Nuclear Regulatory Commission, Washington, D.C.
20555 by the tenth of each month following the calendar month covered by the report.
The monthly report shall include a narrative summary of operating experience describing the operation of the facility, including'ajor safety related maintenance for the monthly period, except that safety related maintenance 6.9-1 PROPOSED
4 4 S l
performed during the refueling outage may be reported in the monthly report for thq month following the end,of the outage rather than each month during the outage.
6.9.2.
Reportable Occurrences Reportable occurrences, including corrective actions and measures to prevent reoccurrence, shall be reported to the NRC.
Supplemental reports may be required to fully describe final resolution of occurrence.
In case of corrected or supplemental
- reports, a licensee event report shall be completed and reference shall be made to the original report date.
6,9-2 PROPOSED
J I'
I N T E N T I 0 N A L L Y B L A N i<
6.9-3 PROPOSED
(2)
Annually:
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according. to work and job functions, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket, dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose peed no/ be a@counted for.
Xn the aggregate, at least 00% of the total whqle body dose received from external sources shall be assigned to specific major work functions.
(NOTE:
This tabulation supplements the requirements of Section 20.407 of 10 'CFR Part 20.)
6.9-10 PROPOSED
I
~
~
'I t
l' lt 0
Table >.13-1 (Continued)
Safeu Nelahe5 Shock Su ressors S~nubbers-Snubber:hark No.
Piping S stem Accessi.ble or Inaccessible (A or I)
High Radiation**
Zone Esoecially Difficult to Remove 4J I
iMW-25 AFK-26 AFW-27 AFW-28 AFW-29 AFW-31 AFW-49 FW-9 FW-30 FW-80 FW-81 "A" Aux. Feedwater
".A" Aux. Feedwater "A" Aux. Feedwater "A"-Aux. Feedwater "A" Aux. Feedwater ItB II Feedwater "B" Feedwater "A" Aux. Feedwater "A" Aux. Feedwater "B" Feedwater
. "B" Feedwater No No No No No No No No No No No No' No No No No No Yes No No No F'."-82 Fec."w; ter No No 0'00 0
0 h
Il C
d'
ATTACHMENT B By letter dated September 16,
- 1977, the NRC requested that the Ginna Technical Specification requirements for the Annual Operating Report be revised.
According to that letter, a review of reporting requirements had been performed and it had been determined that much of the information now included in the Annual Operating Report could be deleted and still meet the desired NRC objectives.
Accordingly, the proposed change would delete-the present requirements for an Annual Operating Report.
Since the NRC has expressed a desire to continue receiving the tabulation of occu-pational exposure data presently required by paragraph 6.9.l.b.(3),
a requirement to submit such information is being retained as Specification 6.9.3.c.(2).
In accordance with the September 16 letter, the Monthly Operating
- Report, beginning with the report for January, 1978 will contain the requested information. It is proposed, however, that the safety re$ ated maintenance performed during the refueling outage be re-ported in the repoxt for the month following the end of the outage.
Because of the extensive maintenance which is performed during the
'pefueli,ng outage, due to the heavy manpower requirements to perform the rqaintenance, the reporting is deferred until. after the outage.
The proposed timing will allow plant personnel at least one month between the end of the outage and the report submittal.
The proposed schedule pill, however, provide maintenance information more frequently than is the case under the present 'Annual Operating Report.
A separate, one-time-only, "Narrative Summary of Operating Experience" to cover the calendar year 1977 will be submitted.
This summary will cover information presently required by Technical Specification 6.9.1.'b.(1) including safety related maintenance.
The proposed change will simplify reporting requirements
- and, will continue to provide to the NRC all information which the September 16, 1977 letter requests.
In addition, a change is proposed to the list of safety related shock suppressors in Technical Specification 3.13-1.
This change would add a hydraulic snubber on the standby auxiliary feedwater to the table.
This snubber is presently installed although the standby auxiliary feedwater system is presently under review at the NRC.
The proposed revision is submitted pursuant to the footnote to Table 3.13-1.
'\\
~E A
I H
I ),