Text

Proposed License Amendment No. 198 to Clean Up Facility
	ML050400207
Person / Time
Site:	Rancho Seco
Issue date:	01/24/2005
From:	Redeker S; Sacramento Municipal Utility District (SMUD)
To:	; Document Control Desk, NRC/FSME
References
	MPC&D 04-120
	Download: ML050400207 (33)
	v • d • e

SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT 0 6201 S Street. P.O. Box 15830, Sacramento CA 95852-1830, (916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA MPC&D 04-120 January 24, 2005 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555 Docket No. 50-312 Rancho Seco Nuclear Generating Station License No. DPR-54 PROPOSED LICENSE AMENDMENT NO. 198 TO CLEAN UP FACILITY OPERATING LICENSE DPR-54 Attention: John Hickman In accordance with 10 CFR 50.90, we are submitting Proposed Amendment No. 198 (PA-198) to Rancho Seco Facility Operating License DPR-54. The proposed license amendment removes unnecessary and obsolete information from the facility operating license. As discussed in Attachment 2, we have concluded that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c). Accordingly, a finding of "no significant hazards consideration" is justified. provides the insertion removal instructions for the affected pages. provides the description and analysis of the proposed change and the No Significant Hazards Consideration. Attachment 3 provides a copy of the revised Facility Operating License pages and Attachment 4 provides a redline/strikeout copy of the affected pages to facilitate NRC review.

In accordance with 10 CFR 50.91(b)(1), we have informed the Radiological Health Branch of the California State Department of Health Services of the proposed amendment by sending them a copy of this submittal package.

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MPC&D 04-120 Members of your staff with questions requiring additional information or clarification may contact Robert Jones at (916) 732-4843.

Sincerely, Steve Redeker Manager, Plant Closure and Decommissioning Attachments (4)

Cc w/ attachments:

B.S. Mallett, NRC, Region IV Radiological Health Branch, California State Department of Health Services

CALIFORNIA ALL-PURPOSE ACKNOWLEDGMENT State of California County of _3 T"ffVA

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NAA4;Aj)A 1q,1rJ0Yn 16r, MM7UGA 0, Name and Title of Officer (e.g., 'Jane Doe. Nofary Publi) 12 -A fVit0' personally appeared t_

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C personally known to me X-proved to me on the basis of satisfactory evidence CHRISTINA KEMMLER Comln~sson # 1391651

-NotyoP~t 6c.Coiltomio to be the person(s) whose name(s) is/are subscribed to the within instrument and acknowledged to me that he/shethey executed the same in his/hefikr authorized capacity(ies),

and that by his/heftIheir signature(s) on the instrument the person(s), or the entity upon behalf of which the person(s) acted, executed the instrument.

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Place Notary Seat Above OPTIONAL Though the information below is not required by law, it may prove valuable to persons relying on the document and could prevent fraudulent removal and reattachment of this form to another document.

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I 0 1997 National Notary Association

9350 De Soto Ave.. P.O. Box 2402

Chatsworth, CA 91313-2402 Prod. No. 5907 Reorder Call Toll-Free 1-800-8764827 Rancho Seco Facility Operating License Proposed License Amendment No. 198 REMOVAL/INSERTION INSTRUCTIONS REMOVE OPERATING LICENSE Pages 1 through 10 INSERT OPERATING LICENSE Pages 1 through 4 Description of the Proposed Change, and No Significant Hazards Consideration

=

Background===

The Sacramento Municipal Utility District (SMUD) shut down Rancho Seco Nuclear Generating Station permanently on June 7, 1989, after approximately 15 years of operation.

On August 29, 1989, SMUD formally informed the NRC that the plant was shut down permanently. On May 20, 1991, SMUD submitted the Rancho Seco decommissioning plan and on March 20, 1995, the NRC issued an Order approving the decommissioning plan and authorizing the decommissioning of Rancho Seco.

SMUD began actively decommissioning Rancho Seco in February 1997, and completed the transfer of all of the spent nuclear fuel to the 10 CFR Part 72 licensed Independent Spent Fuel Storage Installation (ISFSI) on August 21, 2002. Accordingly, the only quality-related structures, systems, or components (SSCs) at the Rancho Seco 10 CFR Part 50 licensed site are the radioactive sources used to calibrate the instrumentation used to measure radioactivity in gaseous and liquid effluents.

Plant dismantlement is substantially complete and most of the SSCs that wvere safety-related or important-to-safety have been removed from the plant and shipped for disposal. The pressurizer was shipped to Envirocare for disposal in April 2004. Removal of the steam generators is in progress. One steam generator was shipped to Envirocare in December 2004, and the second is scheduled for spring 2005. Activities in preparation for the reactor vessel internals segmentation are underway and mobilization of the segmentation contractor is schedule to begin in early 2005.

Description of the Proposed Operating License Change The proposed amendment (PA-198) removes unnecessary and obsolete information from the facility operating license. These changes are editorial and administrative and are consistent with the NRC's desire to improve operating license content by removing inappropriate and unnecessary information. The proposed amendment complies with current regulatory requirements and does not alter or modify any feature associated with the Rancho Seco facility or the site.

Table 1 identifies each section of the operating license and provides a description of the license condition, the proposed revision, and the basis for the proposed change.

As discussed further in this Attachment, we have concluded that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c).

Accordingly, a finding of "no significant hazards consideration" is justified.

No Significant Hazards Consideration SMUD has reviewed the proposed license and PDTS change against each of the criteria in 10 CFR 50.92 and has concluded that the amendment request involves no significant hazards consideration. The following provides SMUD's analysis of the issue of no significant hazards consideration:

1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

No. The proposed changes are administrative and involve deleting unnecessary and obsolete information from the facility operating license. These changes do not affect possible initiating events for accidents previously evaluated or alter the configuration or operation of the facility. Safety limits, limiting safety system settings, and limiting control systems are no longer applicable to Rancho Seco in the permanently defueled mode, and are therefore not relevant.

The proposed changes do not affect the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations. Therefore, the proposed license amendment does not involve, a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed license amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

No. As described above, the proposed changes are administrative. The safety analysis for the facility remains complete and accurate. There are no physical changes to the facility and the plant conditions for which the design basis accidents have been evaluated are still valid.

The operating procedures and emergency procedures are not affected. The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent limits, and have no impact on plant operations. Consequently, no new failure modes are introduced as the result of the proposed changes. Therefore, the proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed license amendment involve a significant reduction in a margin of safety?

No. As described above, the proposed changes are administrative. There are no changes to the design or operation of the facility. The proposed changes do not affect the emergency planning zone, the boundaries used to evaluate compliance with liquid or gaseous effluent

limits, and have no impact on plant operations. Accordingly, neither the design basis nor the accident assumptions in the Defueled Safety Analysis Report (DSAR), nor the Technical Specification Bases are affected. Therefore, the proposed changes do not involve a significant reduction in a margin of safety.

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Revision License Section Section 1 Section 1 is an historical proclamation that is not subject N/A (Subsections L.A to change.

through 1.)

Subsection 2.A Subsection 2.A specifies that the Rancho Seco facility is The specific amendment numbers contained in the described in the Final Safety Analysis Report (FSAR) parenthesis in Section 2.A are no longer accurate. The and the Environmental Report, as supplemented and FSAR has been replaced by the Defueled Safety amended. The FSAR has been replaced by the Defueled Analysis Report (DSAR) and the Environmental Safety Analysis Report (DSAR) and the Environmental Report has been supplemented with the "Supplement Report has been supplemented with the "Supplement to to the Environmental Report - Post Operating Phase."

the Environmental Report - Post Operating Phase."

This subsection is being revised editorially to remove the parenthetical information that names the specific amendment numbers.

Subsection 2.B, Subsection 2.B, Paragraphs (1) through (5) continue to N/A Paragraphs (1) apply and will continue to be implemented by various through (5)

Radiation Protection, Surveillance, and Administrative procedures.

I

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Revision License Section Subsection 2.C, Subsection 2.C, Paragraph (1) establishes the license N/A Paragraph (1) condition that revokes SMUD's authority to operate the reactor. This paragraph continues to apply and is implemented by plant administrative procedures.

Subsection 2.C, Subsection 2.C, Paragraph (2) specifies that the N/A Paragraph (2)

Permanently Defueled Technical Specifications (PDTS) requirements are license conditions and are included in Appendix A to the license. Subsection 2.C, Paragraph (2) also identifies the most recent amendment to the PDTS.

This paragraph continues to apply and will remain unchanged.

Subsection 2.C, This section was deleted in Amendment 131.

N/A Paragraph (3) 2

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Revision License Section Subsection 2.C, Subsection 2.C, Paragraph (4) contains fire protection The fire protection program requirements in the Paragraph (4) requirements that are applicable to an operating nuclear Decommissioning Order are appropriate given the power plant. Decommissioning Order,Section IV(B) permanently shutdown and defueled conditions at the contains updated fire protection program requirements Rancho Seco plant. Since the requirements in for the permanently shutdown and defueled Rancho Decommissioning Order have been incorporated into Seco plant. The requirements in Decommissioning the Rancho Seco DSAR, Subsection 2.C, Paragraph (4)

Order,Section IV(B) have been incorporated into the may be deleted from the operating license.

Rancho Seco Defueled Safety Analysis Report (DSAR).

Since the requirements in Decommissioning Order,Section IV(B) have been incorporated into the Rancho Seco DSAR, Subsection 2.C, Paragraph (4) may be (leleted from the operating license.

Subsection 2.C, Subsection 2.C, Paragraphs (5) and (6) requires These requirements are no longer applicable with Paragraphs (5) supplementary in-service tests and inspections. These Rancho Seco permanently shutdown and defueled.

and (6) requirements are no longer applicable with Rancho Seco permanently shutdown and defueled.

Subsection 2.C, Paragraphs (5) and (6) will be deleted.

3

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Revision License Section Subsection 2.C, Subsection 2.C, Paragraph (7) requires the The type of transients or accidents for which this Paragraph (7) implementation of a leakage reduction program on program was originally intended are no longer systems outside of containment that would or could possible given the decommissioning status of the contain highly radioactive fluids during a serious plant.

transient or accident. The type of transients or accidents for which this program was originally intended are no longer possible given the decommissioning status of the plant.

Accordingly, Subsection 2.C, Paragraph (7) will be deleted.

Subsection 2.C, Subsection 2.C, Paragraphs (8) through (11) were N/A Paragraphs (8) deleted in previous amendments.

through (11) 4

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Rcvision License Section Subsection 2.C, Subsection 2.C, Paragraph (12) addresses NUREG-0737 With all of the spent nuclear fuel in dry storage at the Paragraph (12)

Control Room habitability requirements. With all of the Rancho Seco ISFSI, the Rancho Seco control room is spent nuclear fuel in dry storage at the Rancho Seco no longer in use.

Independent Spent Fuel Storage Installation (ISFSI), the Rancho Seco control room is no longer in use.

Accordingly, Subsection 2.C, Paragraph (7) will be deleted.

Subsection 2.C, Subsection 2.C, Paragraph (13) is an NRC Confirmatory Re-numbering this paragraph to reflect previously Paragraph (13)

Order that prohibits the movement of nuclear fuel into deleted paragraphs is editorial and does not affect the the Rector Building. This paragraph will remain but specific requirement.

will be re-numbered to reflect previously deleted paragraphs.

5

Table 1 Proposed License Revision Facility Description or License Condition and Proposed Reason for Revision Operating Revision License Section Subsection 2.D Subsection 2.D requires SMUD to provide the NRC with Revising Subsection 2.D to reflect that the an analysis, including corrective actions, if the environmental monitoring program requirements have environmental monitoring programs included in the been relocated to the Rancho Seco Quality Manual is Technical Specifications show harmful effects or editorial and does not affect the intend of the license irreversible damage to the environment. The condition or any environmental monitoring program environmental monitoring programs that were previously requirements.

included in the Technical Specifications have been relocated to the Rancho Seco Quality Manual (Appendix A).

This requirement continues to apply and will remain as a license condition. Subsection 2.D will be revised to reflect that the environmental monitoring program requirements have been relocated to the Rancho Seco Quality Manual.

Subsection 2.E This paragraph continues to apply and will remain N/A unchanged.

6

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Revision License Section Order for The Order for Modification of License, dated 07/21/78, The Order for Modification of License, dated Modification of requires a re-evaluation of Emergency Core Cooling 07/21/78, is no longer applicable with Rancho Seco License, dated System performance, provides limits on steady state permanently shutdown and defueled.

07/21/78.

reactor core power, and set a completion time for operator action following accidents that occur during power operations. This Order is no longer applicable with Rancho Seco permanently shutdown and defueled.

Accordingly, this Order will be deleted.

Order for Order for Modification of License, dated 04/01/80, Item With all of the spent nuclear fuel in dry storage at the Modification of

1 concerns the independent verification of valve line-Rancho Seco ISFSI, there is no longer any safety-License, dated ups and equipment operability whenever safety-related related equipment at Rancho Seco. Therefore, the 04/01/80.

equipment is removed from, or placed into, service.

Order for Modification of License, dated 04/01/80, is Items 2 and 3 refer to historical events that happened in no longer applicable.

1980. These items are editorial in nature and may be deleted.

With all of the spent nuclear fuel in dry storage at the Rancho Seco ISFSI, there is no longer any safety-related equipment at Rancho Seco.

Accordingly, this Order will be deleted.

7

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Revision License Scction Order for Order for Modification of License, dated 09/19/80, deals Order for Modification of License, dated 09/19/80, Modification of with the implementation of I&E Bulletin 79-O1B. The deals with the implementation of I&E Bulletin 79-OIB License, dated issues addressed in this bulleting are no longer applicable and is no longer applicable with Rancho Seco 09/19/80.

with Rancho Seco permanently shutdown and defueled.

permanently shutdown and defueled.

Accordingly, this Order will be deleted.

Order for Order for Modification of License, dated 04/20/81, The PCS pressure isolation valve Technical Modification of implements new PCS pressure isolation valve Technical Specification surveillances and LCOs and check valve License, dated Specification surveillances and LCOs and check valve-testing requirements contained in NRC Order for 04/20/81.

testing requirements. These valve-testing requirements Modification of License, dated 04/20/81, are no longer are no longer applicable and have been deleted from the applicable and have been deleted from the Technical Technical Specifications.

Specifications.

Accordingly, this Order will be deleted.

8

Table 1 Proposed License Revision Facility Description of License Condition and Proposed Reason for Revision Operating Revision License Section Order for Order for Modification of License, dated 12/10/82, The reactor coolant inventory monitoring requirement Modification of requires designing and installing an ICC instrumentation specified in NRC Order for Modification of License, License, dated system. This is a reactor coolant inventory monitoring dated 12/10/82, is no longer applicable with Rancho 12/10/82.

issue that comes from NUREG-0737. This requirement Seco permanently shutdown and defueled.

is no longer applicable with Rancho Seco permanently shutdown and defueled.

Accordingly, this Order will be deleted.

Order for Order for Modification of License, dated 05/02/90, This requirement is redundant with Subsection 2.C, Modification of prohibits placing any nuclear fuel into the Rancho Seco Paragraph (13) and may be deleted.

License, dated Reactor Building without prior NRC approval.

05/02/90.

This requirement is redundant with Subsection 2.C, Paragraph (13) and may lbe deleted.

9 Revised Facility Operating License Pages

UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON, DC 20545 SA(lR AMRNTO MIMTNTCIPAL.111T ITY DTISTRITfT DOCKT7 NO 50-312 (RPnchn rh en Nuclear Genernting cStation)

FACILT Y OPER ATINCY TCTFNMRF License No. DPR-54 The Atomic Energy Commission (the Commission) having found that:

A.

The application for license filed by Sacramento Municipal Utility District (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I and all required notifications to other agencies or bodies have been duly made; B.

Construction of the Rancho Seco Nuclear Generating Station (the facility) has been substantially completed in conformity with Construction Permit No.

CPPR-56 and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D.

There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; E.

The licensee is technically and financially qualified to engage in the activities authorized by this operating license in accordance with the rules and regulations of the Commission; F.

The licensee has satisfied the applicable provisions of 10 CFR Part 140, "Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; G.

The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the public; H.

After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of Facility Operating License No. DPR-54, subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied; and I.

The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Part 30, 40, and 70, including 10 CFR Section 30.33, 40.32, 70.23, and 70.31.

2.

Facility Operating License No. DPR-54 is hereby issued to the Sacramento Municipal Utility District to read as follows:

A.

This license applies to the Rancho Seco Nuclear Generating Station, a pressurized water reactor and associated equipment (the facility), owned by the Sacramento Municipal Utility District. The facility is located in Sacramento County, California, and is described in the "Final safety Analysis Report" as supplemented and amended and the Environmental Report as supplemented and amended.

B.

Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Sacramento Municipal Utility District (1)

Pursuant to Section 104b of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess but not operate the facility at the designated location in Sacramento County, California, in accordance with the procedures and limitations set forth in this license; (Amendment 117 - 03/17/92)

(2)

Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources, sealed sources for reactor instrumentation and radiation monitoring equipment, calibration, and as fission detectors in amounts as previously required for reactor operation; and to possess but not use special nuclear material previously received as reactor fuel; (Amendment 117 - 03/17/92)

(3)

Pursuant to the Act and 10 CFR Part 30, to receive, possess, and use at any time 100 millicuries each of any byproduct material, without restriction to chemical or physical form, for sample analysis or instrument calibration; (Amendment 117 - 03/17/92)

(4)

Pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material, without restriction to chemical or physical form, for sample analysis or instrument calibration; (Amendment 117 - 03/17/92)

(5)

Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as were produced by the previous operation of the facility.

(Amendment 117 - 03/17/92)

C.

This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximium Pawer The licensee is not authorized to operate the reactor.

(Amendment 117 - 03/17/92)

(2)

Permnnently Defimled Terhniciil Specifiratinns, The Permanently Defueled Technical Specifications contained in Appendix A, as revised through Amendment No. 131, are hereby incorporated in the license. Sacramento Municipal Utility District shall maintain the facility in accordance with the Permanently Defueled Technical Specifications.

(Amendment 131 - 10/10/02)

(3)

Confirmatorv trder The movement of nuclear fuel into the Reactor Building is prohibited without prior NRC approval.

(Amendment 117 - 03/17/92)

D.

This license is subject to the following additional condition for the protection of the environment:

If harmful effects or evidence of irreversible damage are detected by the monitoring programs included in the Rancho Seco Quality Manual, the Applicant will provide an analysis of the problem and a proposed course of action to alleviate the problem.

E.

This license is effective as of the date of issuance and shall expire at midnight, October 11, 2008.

FOR THE ATOMIC ENERGY COMMISSION Isl ROGER BOYD for A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:

August 16, 1974

Attachment:

Appendix A - Technical Specifications (Amendment 120 - 10/13/92)

I Redline/Strikeout Version of the Affected Pages

UNITED STATES ATOMIC ENERGY COMMISSION WASHINGTON, DC 20545 SACRAMENTO MImCIPAT TI 1n ITYDISTRTCT DO(CKET ND 50-3 19 (Ranchn Sern NMirler Genergtin, Station)

FACI ITY OPFR ATING T JCFNSF.

License No. DPR-54

1.

The Atomic Energy Commission (the Commission) having found that: