NRC Generic Letter 1993-08

NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits

ML031070390
Person / Time
Site:	Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River, Crane
Issue date:	12/29/1993
From:	Callan L Office of Nuclear Reactor Regulation
To:
References
GL-93-008, NUDOCS 9312170112
Download: ML031070390 (7)

-UNITED STATES

NU&

U )kR REGULATORY COMMISSIOk9 WASHINGTON. D.C. 25055 December 29, 1993 TO: ALL HOLDERS OF OPERATING LICENSES FOR NUCLEAR POWER REACTORS

SUBJECT: RELOCATION OF TECHNICAL SPECIFICATION TABLES OF INSTRUMENT RESPONSE

TIME LIMITS (Generic Letter 93-08)

The U.S. Nuclear Regulatory Commission (NRC) is issuing this guidance for requesting a license amendment to relocate tables of instrument response time limits from technical specifications (TS) to the updated final safety analysis report. The NRC developed this line-item TS improvement in response to TS

proposals by applicants for operating licenses.

Licensees that plan to adopt this line-item TS improvement are encouraged to propose TS changes consistent with the guidance given in Enclosures I and 2.

NRC project managers will review the amendment requests to verify that they conform to this guidance. Please contact your project manager or the contact indicated herein if you have any questions on this matter.

Licensee action to propose TS changes under the guidance of this generic letter is voluntary. Therefore, such action is not a backfit under the provisions of Section 50.109 of Title 10 of the Code of Federal Regulations

(10 CFR). The following information, although not requested under the provisions of 10 CFR 50.54(f), would help the NRC evaluate costs and benefits for licensees who propose the TS changes described in this generic letter:

• licensee time and costs to prepare the amendment request

• estimate of the long-term costs or savings accruing from this TS change The voluntary information collections contained in this request are covered by the Office of Management and Budget clearance number 3150-0011, which expires June 30, 1994. The public reporting burden for this voluntary collection of information is estimated to average 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per response, including the time for reviewing instructions, searching existing data sources, gathering and maintaining the data needed, and completing and reviewing the collection of information. Send comments regarding this burden estimate or any other aspect of this voluntary collection of information, including suggestions for reducing this burden, to the Information and Records Management Branch (MNBB-7714), U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, and NRS 7: 002085

19006l

Generic Letter 93-08 -2- .-' December 29, 1993 to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-3019,

(3150-0011), Office of Management and Budget, Washington, D.C. 20503.

Sincerely, A

an Associate Director for Projects Office of Nuclear Reactor Regulation Enclosures

1. Guidance for A Proposed License Amendment to Relocate Tables of Instrument Response Time Limits from Technical Specifications to the Updated Final Safety Analysis Report

2. Model Technical Specifications

3. List of Recently Issued NRC Generic Letters Technical contact: T. G. Dunning, NRR

(301) 504-1189

Generic Letter 93-08 Enclosure 1 Guidance for a Proposed License Amendment To Relocate Tables of Instrument Response Time Limits From Technical Specifications to the Updated Final Safety Analysis Report Introduction The NRC is issuing the following guidance for preparing a proposed license amendment to relocate the tables of response time limits for the reactor trip system (RTS) and the engineered safety features actuation system (ESFAS)

instruments from technical specifications (TS) to the updated final safety analysis report (FSAR). The NRC has already implemented this line-item TS

improvement for recently issued operating licenses and in the improved standard technical specifications.

Discussion The limiting conditions for operation (LCOs) for RTS and ESFAS instruments require that these systems be operable with response times as specified in TS

tables for each of these systems. The surveillance requirements specify that licensees test these systems and verify that the response time of each func- tion is within its limits. Relocating the tables of the RTS and ESFAS

instrument response time limits from the TS to the updated FSAR will not alter these surveillance requirements. The updated FSAR will now address the response time limits for the RTS and ESFAS instruments, including those channels for which the response time limit is indicated as "NA"; that is, a response time limit is not applicable. The updated FSAR will also clarify response time limits where footnotes are included in the tables that describe how those limits are applied. This TS change also allows the licensee to administratively control changes to the response time limits for the RTS and ESFAS instruments in accordance with the provisions of 10 CFR 50.59 without the need to process a license amendment request.

The LCOs for the RTS and the ESFAS typically specify that the associated instruments shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2'

(RTS) or Table 3.3-5' (ESFAS). An acceptable change to the LCOs would be to remove the reference to response times and simply state that this instrumen- tation 'shall be OPERABLE' as shown for the markup of the Westinghouse standard technical specifications in Enclosure 2. This change is applicable to all plants and is compatible with relocating the referenced tables.

The surveillance requirements specify that the response time of each trip function is to be demonstrated to be within its limit at the specified frequency and do not reference the tables of response time limits. Therefore, the surveillance requirements specified in this manner need not be modified to implement this change. However, a footnote in the table of response time limits for the RTS states that neutron detectors are exempt from response time testing. To retain this exception, which is stated in the table being removed from the TS, the surveillance requirements for the RTS should be modified to add the following statement:

Neutron detectors are exempt from response time testing.

Generic Letter 93-08 - 2- Enclosure 1 Each licensee that wishes to implement this line-item TS improvement should confirm that the plant procedures for response time testing include acceptance criteria that reflect the RTS and ESFAS response time limits in the tables being relocated from the TS to the updated FSAR. The licensee should also provide a commitment to include the RTS and ESFAS response time limits in the next update of the FSAR.

Licensees would submit any subsequent changes to these limits in the FSAR as an update of the FSAR as required by 10 CFR 50.71(e). Related changes to plant procedures would be subject to the provisions that control changes to plant procedures as stated in the administrative controls section of the TS.

Generic Letter 93-08 Enclosure 2 K IK

Model Technical Specifications The model technical specifications are based on the Standard Technical Specifications for Westinghouse Pressurized Water Reactors," NUREG-0452, Revision 4a; however, the indicated changes are applicable for all plants.

3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION

3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE. with RESPONSE TIMES as shown in Table 3.34--.

(Change TS 3.3.1 as shown)

4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Neutron detectors are exempt from response time testing. Each test shall include at least one train such that both trains are tested at least once per

36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the 'Total No. of Channels" column of Table 3.3-1.

(Make addition to TS 4.3.1.2 as shown In Bold typeface)

3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION

3.3.2 The Engineered Safety Features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4. end with RESPONSE TIMES as shown inTable 3.3 6.

(Change to TS 3.3.2 as shown)

4.3.2.2 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months.

Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the MTotal No.

of Channels' column of Table 3.3-3.

(Make no change to TS 4.3.2.2)

Lnuluburc a GL 93-08 December 29, 1993

\-J JPage 1 of I

<~

LIST OF RECENTLY ISSUED GENERIC LETTERS

Generic Date of cr. . A-.9- seeumIIane Tstsued To Letter UD-leLL @a,4_, ,

93-07 MODIFICATION OF THE TECH- 12/28/93 ALL HOLDERS OF OLs NICAL SPECIFICATION ADMINI- FOR NPRs STRATIVE CONTROL REQUIRE-

MENTS FOR EMERGENCY AND

SECURITY PLANS

93-06 RESEARCH RESULTS ON 10/25/93 ALL HOLDERS OF OLs OR

ON GENERIC SAFETY ISSUE 106, CPs FOR NPRs

'PIPING AND THE USE OF

HIGHLY COMBUSTIBLE GASES IN

VITAL AREAS

93-05 LINE-ITEM TECHNICAL 09/27/93 ALL HOLDERS OF OLs.OR

SPECIFICATIONS IMPROVE- CPs FOR NPRs MENTS TO REDUCE SURVEILLANCE

REQUIREMENTS FOR TESTING

DURING POWER OPERATION

89-10, INACCURACY OF MOTOR- 06/28/93 ALL LICENSEES OF

SUPP. 5 OPERATED VALVE OPERATING NUCLEAR POWER

DIAGNOSTIC EQUIPMENT PLANTS AND HOLDERS OF

CONSTRUCTION PERMITS FOR

NUCLEAR POWER PLANTS

93-04 ROD CONTROL SYSTEM 06/21/93 ALL HOLDERS OF OLs OR

FAILURE AND WITHDRAWAL CPs FOR (W)-DESIGNED

OF ROD CONTROL CLUSTER NPRs EXCEPT HADDAM NECK

ASSEMBLIES, 10 CFR 50.54(f)

ALL HOLDERS OF OLs OR

CPs FOR (CE)-DESIGNED

AND (B&W)-DESIGN NPRs AND HADDAM NECK

93-03 VERIFICATION OF PLANT

• 10/20/93 ALL HOLDERS OF OLs OR

RECORDS CPs FOR NPRs

93-02 NRC PUBLIC WORKSHOP ON 03/23/93 ALL HOLDERS OF OLs OR

COMMERCIAL GRADE PRO- CPs FOR NPRs AND ALL

CUREMENT AND DEDICATION RECIPIENTS OF NUREG-0040,

"LICENSEE CONTRACTOR AND

VENDOR INSPECTION STATUS

REPORT* (WHITE BOOK)

OL = OPERATING LICENSE

CP - CONSTRUCTION PERMIT

NPR - NUCLEAR POWER REACTORS

'K)

Generic Letter 93-08 -2- December 29, 1993 to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-3019,

(3150-0011), Office of Management and Budget, Washington, D.C. 20503.

Sincerely, orig /s/'d by LCWallan L. J. Callan Acting Associate Director for Projects Office of Nuclear Reactor Regulation Enclosures:

1. Guidance for A Proposed License Amendment to Relocate Tables of Instrument Response Time Limits from Technical Specifications to the Updated Final Safety Analysis Report

2. Model Technical Specifications

3. List of Recently Issued NRC Generic Letters Technical contact: T. G. Dunning, NRR

(301) 504-1189 DISTRIBUTION:

NRC PDR

Central Files DORS R/F

OTSB R/F

FJMiraglia WTRussell JGPartlow SATreby BKGrimes GHMarcus ClGrimes FMReinhart WAReckley TGDunning As confirmed by D. Allison, CRGR staff on 12/06/93, further CRGR review was not considered necessary because no substantive changes were made to the generic letter as reveiwed by CRGR in response to public comments.

• SEE PREVIOUS CONCURREN(

OTSB:DORS Tech Ediltor OTSB:DORS C:OTSB:DORS C:OGCB:DORS

TGDunning;tgd* MMeJac* FMReiyrt* CIGrimes* GHMarcus*

07/29/93 07/29/93 } 8 4'93 09/07/93 09/08/93 PDIV-2 OGC ,46S$jRR ADP: NRR

WAReckley* SATreby* <2GP4Ifes LJCal 1an*

09/09/93 09/14/93 12/i./93 12/22/93 DOC NAME: 93-08.IN