ML16337A343

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Conversation Record - Changes to the Technical Specifications in Support of License Renewal
ML16337A343
Person / Time
Site: University of Maryland
Issue date: 12/02/2016
From: Eben Allen
NRC/NRR/DPR/PRLB
To: Andrea Johnson, Koeth T
Univ of Maryland
Eben Allen
References
TAC ME1592
Download: ML16337A343 (2)


Text

NRC FORM 699 /'-.~ U.S. NUCLEAR REGULATORY COMMISSION DATE OF SIGNATURE (03-2013)  !~ ~

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... ..... *'" CONVERSATION RECORD i z../z. //£ NAME OF PERSON(S) CONTACTED OR IN CONTACT WITH YOU DATE OF CONTACT TYPE OF CONVERSATION D E-MAIL Timothy Koeth; Amber Johnson 12/02/20 16 E-MAIL ADDRESS TELEPHONE NUMBER IZI TELEPHONE D INCOMING koeth at umd.edu; ajohns37 at umd.edu IZI ORGANIZATION DOCKET NU MBER($)

. OUTGOING University of Maryland 05000 166 LICENSE NUMBER($) CONTROL NUMBER(S)

R-70 ME1592 SUBJECT Changes to the technical specifications in support of license renewal

SUMMARY

During the review fo r the renewal of Facility Operating License No. R-70, for the Maryland University Training Reactor, dated May 12, 2000, (a redacted version of the application, including the safety analysis report, is available on the Nuclear Regulatory Commission's (NRC) public Web site at www.nrc.gov under Agencywide Documents Access and Management System (ADAMS)

Accession No. ML0037 I 8746), as supplemented, the NRC staff identified areas were the submitted materials contained conflicting, or unclear information.

The phone call placed on December 2, 2016, discussed with the licensee areas where additional clarity was needed. The licensee agreed to supplement the technical specifications subm itted by letter dated November 17, 2016 (A DAMS Accession No.

ML I 6323A447), to continue the review of the license renewal.

Continue on Page 2 ACTION REQUIRED (IF ANY)

The licensee shall respond by e-mail to the NRC staff's items on the following page.

Continue on Page 3 NAME OF PERSON DOCUMENTING CONVERSATION Eben Allen SIGNATURE a_c- ~

NRC FORM 699 (03-2013)

Page 1 of 2

NRC FORM 699 U.S. NUCLEAR REGULATORY COMMISSION (03-2013)

CONVERSATION RECORD (continued)

SUMMARY

(Continued from page 1)

The regulation in Title 10 of the Code of Federal Regulations ( 10 CFR) 50.21(c) provides for issuance ofa license to a facil ity which is useful in the conduct of research development activities if no more than 50 percent of the annual cost of owning and operating the facility is devoted to production of materials, products, or the sale of services, other than research and development or education or training.

Does the MUTR facility devote less than 50 percent of the cost of operating the fac ility to commercial activities?

The licensee answered that less than 50 percent off the cost ofowning and operating the MUTR facility is devoted to commercial purposes.

Technical Specification (TS) are derived from the analyses and evaluations included in the safety analysis report. Due to the importance to overall facility safety interpretation by both the li censee and regulator for terms and phrase used in TS, definitions shall be included where necessary to ensure that the TS criteria necessary for compliance with regulatory requirements are uniformly understood by the licensee and regulator. Guidance pertaining to the format and content of TS previously found acceptable by the NRC staff is provided in NUREG-1537 Part I, and ANSl/ANS- 15.1 -2007.

The following TSs were discussed as having safety significance, the licensee agreed to make changes to clarify the intention of the specification and to correct errors.

Definition Scram Time - The definition is referred to as drop time in the preceding TSs.

TS 3.1 Specification I - An analysis submitted December 18, 2006 was completed at $1.12 not the specification limit of $3.50.

TS 3.1 Specification 2 (b) - In-core experiments do not account fo r al l experi ments.

TS 3.1 Specification 4 - This specification contains redundant information.

TS 3.1 Specification 4 (a) - This specification does not clearly coincide with TS 4.1 Specification 4.

TS 3.1 Specification 4 (b) - This specification does not clearly coincide with TS 4.1 Specification 4.

TS 3.5.1 Specification I - The bridge monitor is needed to be OPERA TING.

TS 3.5.1 Specificatio n 2 - This specification requires clarification.

TS 3.5.1 Specificatio n 3 - This specification does not clearly coincide with TS 3.5.1 Specification I.

Table 3.5 - The table does not accurately depict the operational state of the MUTR facility.

TS 3.6 Specification 2 - In-core experiments do not account for all experiments.

TS 4 Specification - The wording above the table does not coincide with the table.

TS 4.1 Specification 4 - The specification dose not clearly coincide with TS 3. 1 Specification 4.

NRC FORM 699 (03-2013)

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