ML19250C468
| ML19250C468 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/15/1979 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | Wofford A LONG ISLAND LIGHTING CO. |
| References | |
| NUDOCS 7911260244 | |
| Download: ML19250C468 (9) | |
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UNITED STATES NUCLEAR REGULATORY COMMISS ON e
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..gg 151979 Docket No.: 50-322 Mr. Andrew W. Wofford Vice President Long Island Lighting Company 175 East Old Country Road Hicksville, New York 11801
Dear Mr. Wofford:
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION - SHOREHAM NUCLEAR POWER STATION In order to complete our review of the Shoreham application, we require adequate responses to the enclosed requests for additional information.
If you have any questions on this matter, please contact us.
Sincerely, Vsrp>uSE;b L. S. Ru nstein, Acting Chief Light Water Reactors Branch No. 4 Division of Project Management
Enclosures:
As stated cc w/ enclosures:
See next page 1388 015 791126o2#4
Long Island Lighti'ng Company ccs:
Howard L. Blau, Esq.
Blau and Cohn, P.C.
217 Netbridge Road Hicksville, New York 11801 Jeffrey Cohen,Esq.
Deputy Comnissioner and Counsel New York State Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Energy Research Group, Inc.
400-1 Totten Pond Road Waltham, Massachusetts 02154 Irving Like, Esq.
Reilly, Like and Schnieder 200 West Fbin Street Babylon, New York 11702 J. P. Novarro Project Manager Shoreham tbclear Poker Station P. O. Box 618 Wading River, New York 11792 W. Taylor Reseley, III, Esq.
Hunton & Willians P. O. Box 1535 Richmond, Virginia
?3212 Ralph Shapiro, Esq.
Caramer & Shapiro No. 9 East 40th treet New York, New York 10016 Edward J. Walsh, Esq.
General Attorney Long Island Lighting Company 250 Old Cour.try Road Mineola, New York 11501 1388 016 w
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121.0 MATERIALS ENGINEERING BRANCH - MATERIALS INTEGRITY SECTION 121.21 We require that your inspection program for Class 1, 2 and 3 components be in accordance with the revised rules in 10 CFR Part 50, Section 50.55a, paragraph (g). Accordingly, submit the following infomation:
(1) A preservice inspection plan which is consistent with the required edition of the ASME Code. This inspection plan shoM include any exceptions you propose to the Code requirements.
(2) An inservice inspection plan submitted within six months of the anticipated date for comercial operation.
This preservice inspection plan will be required to support the safety evaluation report finding regarding your compliance with prescryice and inservice inspection requirements. Our detemination of your compliance will be based on:
(1) That edition of Section XI of the ASME Code referenced in your FSAR or later editions of Section XI referenced in the FEDERAL REGISTER tnat you may elect.o apply.
(2) All augmented examinations established by the Commission when added assurance of structural reliability was deemed necessary. Examples of augmented examination requirements can be found in the NRC positions on:
(1) high energy fluid systems in Section 3.6 of the Standard Review Plan (SRP), NUREG-75/087; (2) turbine disk integrity in Section 10.2.3 of the SRP; (3) the BWR feedwater inlet nozzle inner radii, NUREG-312, and (4) BWR SS piping NUREG-313.
Your response to this item should define the applicable edition (s) and subsections of Section XI of the ASME Code.
If any of the examination requirements of the particular edition of Section XI you referenced in the FSAR cannot be met, a request for relief must be submitted, including complete technical justification to support your request.
Detailed guidelines for the preparation and content of the inspection programs to be su'ynitted for staff review and for relief requests are attached as Appendix A to Section 121.0 of our review questions.
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l?.1-2 121.22 Supply the pressure-temperature limits for SNPS-1 for the following (Tech Specs) conditions:
(1) Heatup-cooldown (2) Nomal operaticns (3) Inservice leak and hydrostatic tests Specify the number of effective full power years that these limits are to be applicable, the predicted fluence at the quarter thickness wall location, the radius and thickness of the. reactor vessel, and any assumptions used in calculating these limits.
121.23 To demonstrate compliance with Apper. dix H to 10 CFR Part 50, include in the SNPS-1 FSAR and Technical Specifications a table that provides the following information for each surveillance specimen capsule:
(1) The actual surveillance materials in each capsule, (2) The beltline material from which each surveillance material was
- obtained, (3) The test specimen type (s), and their orientation, for each surveillance material, (4) The actual location of each capsule in the reactor vessel, (5) The lead factor for each capsule calculated with respect to the is wall thickness location, (6) The proposed loading schedule of the capsules into the WNP-2 reactor vessel, and (7) The proposed time of capsule withdrawal (calender years and effective full power years).
Also, state the ASME Code requirement (specify edition, addenda, section and paragraph), the ASTM Standard (specify number and year),
or any other document from which the materials surveillance program for SNPS-1 was fomulated.
121.24 It is our position that the construction and inspection of the RSP reactor surveillance capsule attachments be done according to the requirconts for permanent structural attachments to reactor vessels specif.ed in ASME Code Sections III and XI.
121.25 Specify the fracture toughness requirements imposed on the ferritic materials used in the piping, pumps and valves, and bolting over one inch nominal diameter, used in the reactor coolant pressure boundary of SNPS-1.
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APPENDIX A GUIDANCE FOR PREPARING PRESERVICE AND INSERVICE INSPECTION PROGRAMS AND RELIEF REQUEST PURSUAMi T0 10 CFR 50.55a(g)
A.
Description of the Preservice/ Inservice Inspection Pro. gram This program should cover the requirements set forth in Section 50.55a(g) of 10 CFR Part 50 and the ASME Boiler and Pressure Vessel Code,Section XI, Subsections IWA, IWB, IWC and IWD. The guidance provided in this enclosure is intended to illustrate the type and extent of infonnation that should be provided for NRC review.
It also describes the infonnation necessary for " request for relief" of items that cannot be fully inspected to the requirements of Section XI of the ASME Code. By utilizing these guidelines, licensees can significantly reduce the need for requests for additional infonnation from the WRC staff.
B.
Contents of the Submittal The infonration listed below should be included in the submittal:
- 1.
For each facility, include the applicable date. of the ASME Code and the appropriate addendum date.
2.
The period and interval for which this program is applicable.
3.
Provide the proposed codes and addenda to be used for repairs, modifications, additions er alternations to the facility which might be implemented during this inspection period.
4.
Indicate the examinations that you have exempted under the rules of Section XI of the ASME Code. A reference to the applicable paragraph of the code that grants the exemption is satisfactory.
The inspection requirements for exempt components should be stated (e.g., visual inspection during a pressure test).
5.
Identify the inspection and pressure testing iequirements of the applicable portion of Section XI that are deemed impractical because of the limitation of design, geometry or materials of construction of the components. Provide the information requested in the following section of this appendix for the inspections and pressure tests identified in Item 4 above.
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. C.
Request for Relief from Certain Inspection and' Testing Requireacnts It has been the staff's experience that many requests :or relief from t.esting requirements submitted by licensees have not been supported by adequate descriptive and detailed technical information. This detailed infomition is necessary to:
(1)decumenttheimpracticality vf the ASME Code requirements within the limitations of design, geometry and materials of construction of components; and (2) determine whether the use of alternatives will provide an acceptJ1e level of quality and safety.
Relief request submitted with a justification such as " impractical,"
" inaccessible," o, any other categorical basis, require additional infomation to pemit the staff to make an evaluation of that relief request. The objective of the guidance provided in this section is to illustrate the extent of the infomation that is required by the NRC staff to make a proper evaluation and to adequately document the basis for granting the relief in the staff's Safety Evaluation Report. The NRC staff believes subsequent requests for additional information and delays in completing the review can be considerably reduced if this infomation is provided initially in the licensee's submittal.
For each relief request submitted, the following information should be included:
1.
An identification of the component (s) and/or the examination requirement for which relief is requested.
2.
The number of items associated with the requested relief.
3.
The ASME Code class.
4.
An identification of the specific ASME Code requirement that has been detemined to be imptactical.
5.
The infomation to support the detemination that the requirement is impractical; i.e., state and explain the basis for requesting relief.
6.
An identification of the alternative examinations that are proposed:
(a) in lieu of the requiraments of Section XI; or (b) to supplement examinations performed partially in compliance with the requirements of Section XI.
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. 7.
A description and justification of any changes expected in the overall level of plant safety by performing the proposed alternative examinations in lieu of the examination required by Section XI.
If it is not possible to perform alternate examinations, discuss the impact on the overall level of plant quality and safety.
For inservice inspection, provide the following additional information regarding the inspection frequency:
8.
State when the request for relief would apply during the inspection period or interval (i.e., whetner the request is to deferanexamination).
9.
State when the proposed alternative examinations will be implemented and perfomed.
- 10. State the time period for which the requested relief is needed.
Technical justification or data must be submitted to support the relief request. Opinions without substantiation that a change will not affect the quality level are unsatisfactory.
If the relief is requested for inaccessibility, a detailed description or drawing which depicts the inaccessibility must accompany the request. A relief request is not required for tests prescribed in Section XI that do not apply to your facility. Astatementof"N/A"(not applicable) or "None" will suffice.
D.
Request for Relief for Radiation Considerations Exposures of test personnel to radiation to accomplish the examina-tions prescribed in Section XI of the ASME Code can be an important factor in detemining whether, or under what conditions, an examina-tion must be perfomed. A request for relief must be submitted by the licensee in the manner described above for inaccessibility and must ha subsequently approved by the NRC staff.
We recognize that some of the radiation considerations will only be known at the time of the test. However, the licensee generally is aware, from experience at operating facilities, of those areas where relief will be necessary and should submit as a minimum, the following information with the request for relief:
1.
The total estimated man-rem exposure involved in the examination.
2.
The radiation levels at the test area.
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. 3.
Flushing or shielding capabilities which might reduce radiation levels.
4.
A proposal for alternate inspection techniques.
5.
A discussion of the considerations involved in remote inspections.
6.
Similar welds in redundant systems or similar welds in tha same systems which can be inspected.
7.
The results of preservice inspection and any inservice results for the welds for which the relief is being requested.
8.
A discussion of the consequences if the weld which was not examined, did fail.
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Enclosure 212.0 REACTOR SYSTEMS BRANCH 212.107 W';n.espect to the means to cope with passive failures during the long term post-LOCA period (refer to NRC Staff Question Nos. 212.72 and 212.102), provide appropriate plan and elevation drawings of the annular area between the suppression pool and the reactor building where ECCS equipment is located. The information should include equip-ment general arrangement drawings in this annular region, is well as piping isometric drawings which clearly distinguish to whi.:h of the safety systems the piping is associated with. Also show the location and elevation of sumps for draining water which has leaked into the annular area.
It is particularly important that you complete your response to our previous Question Numbers 212.72 and 212.102. We need complete responses to these questions before we can complete our review in this area.
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