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UNITED STATES 4
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waswiNorow o.c.aceos MAY 181984 MEMORANDUM FOR: Thomas T. Martin, Director Division of Engineering Region I FROM:
Richard H. Vollmer, Director Division of Engineering Office of Nuclear Reactor Regulation SU8 JECT:
REGION ! ASSISTANCE TO THE O! VISION OF ENGINEERING We have been fortunate to have had Mr. Kamal Manoly of your division assigned to assist in the review and resolution of allegations pertaining to pipe supports at the Diablo Canyon Plant. Mr. Manaly has provided a dimension of inspection experience, technical expertise with regard to pipe supports and leadership that are an essential element of the program to complete the Diablo Canyon licensing process. Mr.
Manoly's continued participation is essential to the timely completion of this effort.
In its order of April 18, 1984, enclosed, the Comission set forth license conditions growing out of the staff review and inspections associated with resolution of pipa support allegations. We are now in the process of reviewing the licensees programs to address these conditions. Mr. Manoly has been at, signed responsibility as a task group leader for one of the conditions and 1s a key member of the task groups charged with review of two other issues. Consistent with the February 9,1984 memorandum from the E00 to J. Martin, Regional Administrator, Region V concerning Regional and Headquarters personnel assigned to review of piping allegations at Diablo Canyon we. assume that Mr. Manoly will continue to be available through culmination of the activities listed below.
Anticipated Schedule May 14 -17 Audit in San Francisco, CA. Condition 1 May 29 -June 1 Audit in San Francisco, CA. Conditions 1 and 7 i
June 4 -June 7 Drafting of Inspection and Audit Report June 10-June 14 Audit of IDVP in San Francisco, CA.
June 18-June 22 Confimatory audits as required in San Francisco and San Luis Obispo, CA.
June 25-June 28 Preparation of final Safety Evaluation.
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Richard H. Vollmer, Director Division of Engineering
Enclosure:
As stated l
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H. Denton T. Murley D. Eisenhut J. Knight T. Novak R. Bosnak G. Knighton S. Ebneter H. Schierling M. Hartzman K. Manoly
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APR 181984 i
Docket No.: 50-275 Mr. J. O. Schuyler, Vice President Nuclear Power Generation l
c/o Muclear Power Generation, Licensing I
Pacific Gas & Electric Company 77 Beale Street, Room 1435 San Francisco, California 94106
Dear Mr. Schuyler:
Subject:
Order to Modify Facility Operating License No. OPR-76 (Diablo Canyon Nuclear Power Plant, Unit 1)
The 'Juclear Regulatory Comission has issued the enclosed Sub.iect Order. The Order sets forth License Condition 2.C.(11) which amends the license. The condition pertains to certain piping and piping support efforts that must be ecmpleted by Pacific Gas & Electric Company prior to Diablo Canyon Unit 1 ccerating above 5 percent of rated power.
The staff intends to audit and evaluate your efforts as they progress, including observation of the plant walkdowns. We recuest that you infom us as early as possible of your schedule 'or the hot walkdown of the main feedwater systen piping to he perfomed af ter exceeding 5 percent power.
The enclosed Order will be forwarded to the office 'n' the Federal Register for l
publication.
Sincerely, c
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Divison of Lidensing l
Office of fluclear Reactor Regulation
Enclosure:
Order to ifadify Facility Operating License No. OPR-76 l
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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PACIFIC GAS & ELECTRIC COMPANY
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Docket No. 50-275 (Diablo Canyon Nuclear Power
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Plant, Unit 1)
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CROER MODIFYING LICENSE I.
The Pacific Gas and Electric Company (PG&E or the Licensee) holds License No. OPR-76 which authori:es the Licensee to conduct low power coeration of the Jiablo Canyon Nuclear Power Plant, Unit 1, at up to 5%
of the facility's rated power. The license was issued on September 00, 1931, and was recently fully reinstated by the Commission af ter having teen suspended in Novem er 1981 pending the successful completion of an incepeacent design verification program.
II.
Ouring the staff's review of the results of the independent design verification program and other matters related to the readiness of Diablo Canyon Unit 1 for low-power operation upon reinstatement of the sus-conced license, a numcer of concerns were rair,ed regarding the adequacy of tne 3e$199 and design control measures for piping and piping supoorts.
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p attention to these concerns to ensure that the piping and piping supports would not pose an undue risk to public health and safety if Diablo Canyon Unit I were permitted to operate at low power.
Among its evaluations and inspections of the piping issue, the staff convened a peer review group of technical experts to review certain concerns raised by Mr. Isa Yin, an NRC inspector who had reported, on the basis *of his review and inspection, inadequate compliance with design requirements', dpcu-ment controls and personnel training for piping and piping supports. The peer review groue met with Mr. Yin, pG&E representatives, and some of the contractors involved in the independent design verification program. The groue visited Diablo Canyon, and later met with Mr. Charles Stokes, a former employee at the Diablo Canyon project site who had made allegations concern-ing tne adecuacy of small-bore piping and piping supports. The group later et alth Mr. Yin to discuss the group's proposed findings.
In addition to tre staf *'s reviews and inspections of the piping and piping supports, the Acvisory Committee on Reactor Safeguards (ACRS) met in public session on 4:ril 6,1934, to hear from Mr. Yin, other members of the NRC staf f, and Mr. Ston.es.
The peer rev'iew group and the ACRS concluded that Mr. Yin's concerns did not warrant delaying low-power operation of Diablo Canyon Unit 1.
Mr. Yin informed the ACRS that, upon further review of the matter, he did not believe that resolution of the piping issues required further deferral of the reinstatement of the low-power operating license for Otablo Canyon Unit i Ac:orcingly, the Commission reinstated the low power license on Ac t' 13, 1934 Spe3 CLI-94-5. at 4-6.
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3-The peer review g'rcup, the ACRS, and Mr. Yin agree that the piping issue requires resolutfun prior to authorizing' full power operation of' I
Diablo Canyon Unit 1.
On the basis of the various reviews of this matter, the staff believes that a number of actions are necessary to j
ensure the adequacy of small and large-bore piping and pipe supports and to ensure correction of deficiencies, if any, before Diablo Canyon'
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Unit 1 can be permitted to operate above 5% rated power.
III.
Accordingly, pursuant to sections 103,161(1),161(o),182 and 186 of the Atomic Energy Act of 1954, as amended, and 10 CFR 2.204 and 10 CFR Part 50 of the Commission's regulations, IT IS HEREBY ORDERED THAT the Licensee shall not operate Diablo Canyon Unit I above 5's power until the Licensee has completed the specific actions which are set forth below in new License Condition 2.C.(11) to Facility Operating License No. OPR-76:
- 2. C. ( 11) : pioina and piping Supoorts
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PG&E shall complete the review of all small-bore piping supports which were reanalyzed and requalified by computer analysis. The review shall include consideration of the additional technical topics, as appropriate, contained in License Condition No. 7 below.
2.
PG&E shall identify all cases in wnich rigid supports are placed in close proximity to other rigid supports or anchors. For these cases PG&E shall conduct a program that assures loads shared between these 9
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e adjacent supports and anchors' result in acceptable piping and support stresses. Upon completion of this effort, PG&E shall submit a report to the NRC staff documenting the results of the program.
3.
PG&E shall identifv all cases in which snubbers are placed in close proximity to rigid supports and anchors. For these' cases,
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utilizing snubber lock-up motion criteria acceptable to the staff;.
PG&E shall demonstrate that acceptable piping and piping support stresses are met. Upon completion of this effort, PG&E shall submit a report to the NRC staff documenting the results.
4 PG&E shall identify all pipe supports for which thermal gaps have been specifically included in the piping thermal analyses. For these cases the licensee shall develop a program for periodic inservice inspection to assure that these thermal gaps are main-tained throughout the operating life of the plant. PG&E shall sub-mit to the NRC staff a report containing the gap monitoring program.
5.
PG&E shall provide to the NRC the procedures and schedules for the
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hot walkdown of the main steam system piping. PG&E shall document the main steam hot walkdown results in a report to the NRC staff.
6.
PG&E snall conduct a review of the " Pipe Support Design Tolerance Clarification" program (PSOTC) and "Diablo Problem" system (0P) activities. The review shall include specific identification of tne following:
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(a) Support changes which deviated from the defined PSOTC program scope; (b) Any significant deviations between as-brillt and design configur-ations stemming from the PSDTC or DP activities; and (c) Any unresolved matters identified by the OP system.
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The purpose of this review is to ensure that all design changes and modifications have been resolved and documented in an appropriate manner.
Upon completion PG&E shall submit a report to the NRC staff documenting the results of this review.
7.
pG&E shall conduct a program to demonstrate that the fol1$1ng technical topics have been adequately addressed in the design of small and large-bore piping supports:
4 (a)
Inclusion of tarping normal and shear 5, tresses cdOto torsion in those open sections where warping effects are significant.
(b) Resolution of differences between the AISC Coce and Bechtel criteria with regard to allowable lengths of unbraced angle
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(c) Consideration of lateral / torsional buckling under axial loacing
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(d) -Inclusion of axial and torsional loads due to load eccentricity where appropriate.
1 Correct calculation of pipe support fundamental frequency by (e)
Rayleigh's method.
3R (f) Consideration of flare bevel weld effective throat thickness-as used on structural steel tubing with an outside radius of less than 2T.
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O PG&E shall submit a report to the NRC staff documenting the the results of the program.
3.
The Di/ect.or, Division of Licensing, Office of Nuclear Reactor Regulation, may relax any of the foregoing conditions for. good cause.
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IV.
The Licensee may request a hearing on this Order. Any request for lIp a hearing on this Order must be submitted within 20 days of the date of-
- this Order to the Director, Division of Licensing, Office of Nuclear Reactor Regul tion, U.S. Nuclear Regulatory Commission,. Washington,- D.C.,
t 20555. A copy of the request shall also be sent to the Executive Legal Director, U.S.N.R.C., Wasnington, D.C., 20555.
If a hearing is to be held, the Commission will issue an Crear des'gnating the dime and place of any such hearing.
If a nearing is m
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should be sustained.
This Order shall become effective without further proceedings upon the Licensee's consent to the Order or upon expiration of the period within which the Licensee may request a hearing.
If the Licensee requests a hearing this Order shall be effective in accordance with an Order issued
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following further proceedings on this Order.
FOR THE NUCLEAR REGULATORY COMMISSION a re s'en u DivisionofMicensing Office of Nuclear Reactor Regulation Dated at 8ethesda, Maryland, this 18thcay of April,1984
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