ML19326D611

Forwards Response to IE Bulletin 80-06, Engineered Safety Feature (ESF) Reset Controls. List of safety-related Equipment Which Will Not Remain in Emergency Mode After Reset of Actuation Signals Encl

ML19326D611
Person / Time
Site:	Sequoyah
Issue date:	06/12/1980
From:	Cross J TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
IEB-80-06, IEB-80-6, NUDOCS 8007020740
Download: ML19326D611 (3)

Text

.

TENNEOCEE V/.LLEY AUTHORITY gy

^ ~'

CHATTANOO2A. TENNEC*EE 374ot 500A Chestnut Street Tower II

& Sp y I p a s l ,-

v..e 7.' s, June 12, 1980 Mr. Janes P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II - Suite 3100 101 Marietta Street Atlanta, Georgia 30303

Dear Mr. O'Reilly:

OFFICE OF INSPECTION AND ENFORCEMENT BULLETIN 80 RII:JP0 50-327 -

SEQUOYAH NUCLEAR PLANT UNIT 1 In response to your letter dated March 13, 1980, which transmitted Inspection and Enforcement Bulletin 80-06 on Engineered Safety Features Reset Controls, we are enclosing the results of our investigation for Sequoyah Nuclear Plant unit 1. As stated in the enclosure, TVA has not completed the required testing, redesign, and modifications. We expect to submit monthly progress reports until the requirements of the bulletin have been met. We will submit our next report on this bulletin on July 11, 1980.

If you have any questions concerning this matter, please get in touch with D. L. Lambert at FTS 857-2581.

Very truly yours, TENNESSEE VALLEY AUTHORITZ h

J. L. Cross Executive Assist (nt to the Manager of Power Enclosure ec: Director, Division of Reactor Operations Inspection (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Sworn to and subscribed before me s/ day of An/1980 J%f '

.1Ast-Notarf Public My Commission Expires #fF ~ ~

//

An Eaual Opportunity Emcicyer

. . - . g n n r og o Wo.. .- . ... . . . . - -.

t ENCLOSURE SEQUOYAli NUCLEAR PIMI UNIT 1 RESPONSE TO IE BULLETIN 80-06 ENGINEERED SAFETY FEATURES RESET CONTROLS The drawing review, as requested in item 1 of the bulletin, is complete.

Safety-related equipment which will not remain in the emergency mode after reset of ESF actuation si tnals is listed below.

FCV-3-35A SG 1 Inlet Flow Control Valve Bypass Valve FCV-3-48A SG 2 Inlet Flow Control Valve Bypass Valve FCV-3-90A SG 3 Inlet I' low Control Valve Bypass Palve FCV-3-103A SG 4 Inlet Flow Control Valve Bypass Valve FCV-3-35 SG 1 W Inlet Flow Control Valve FCV-3-48 SG 2 W Inlet Flow Control Valve FCV-3-90 SG 3 W Inlet Flow Control Valve FCV-3-103 SG 4 W Inlet Flow Control Valve LCV-3-172 SG 3 Level Control Valve LCV-3-173 SG 2 Level Control Valve LCV-3-174 SG 1 Level Control Valve .

LCV-3-175 SG 4 Level Control Valve LIC-3-172 SG 3 Level Indicating Controller LIC-3-173 SG 2 Level Indicating Controller LIC-3-174

• SG 1 Level Indicating Controller ,

LIC-3-175 SG 4 Level Indicating Controller l LCV-3-148 SG 3 Level 7alve LCV-3-156 SG 2 Level Valve LCV-3-164 SG 1 Level valve LCV-3-171 SG 4 Level Valve LCV-3-148A SG 3 Level Bypass Control Valve LCV-3-156A SG 2 Level Bypass Control Valve LCV-3-164A SG 1 Level Bypas! Control Valve LCV-3-171A SG 4 Level Bypass Control Valve LIC-3-148 SG 3 Controller LIC-3-156 SG 2 Controller LIC-3-164 SG 1 Controller LIC-3-171 SG 4 Controller FCO-30-122 Cask Loading Area Exhaust Damper FCO-30-123 Cask Loading Area Exhaust Damper '

FCO-31A-17 Spreading R.on Supply Fan FCO -31A-102 Spreading Room Supply Fan FCO-31A-103 Toilet and Incker Room Exhaust Fan .

FCO-31A-104 Toilet and Locker Room Exhaust Fan FCO-31A-105A,B,D . Main Control and Spreader Roca Fresh Air ~.

Isolation Dampers

~

FCO-31A-106A,B,C Main Control and Spreader Room Fresh Air Isolation Dampers

• , e e . e S

9

.. . . .,. . .... .. . _ . _ . _ ~ . . . . ,_ . ..

, , . - --n--~ _ -- -

FCV-74-16 (HCV-606) RER Heat Exchanger A Outlet Flow Control Valve FCV-74-28 (HVC-607) RER Heat Exchanger A Outlet Flow Control Valve FCV-1-51 Aniliary Feed Pump Turbine Trip and Throttle Valve FCV-1-52 Auxiliary Feed Pump Turbine Speed Control PCV-65-81 & 86 Shield Building Tent Isolator Valve and Containment Ansulus Isolator Valve Train A PCV-65-83 & 87 Shield Building Vent Isolator Valve and Containment Annulus Isolator Valve Train B FCV-43-55 Steam Generator No. 1 Building Isolator Valve FCV-43-58 Steam Generator No, 2 Building Isolator Valve FCV-4 3-61 Steam Generator No. 3 Euilding Isolator Valve FCV-43-64 Steam Generator No. 4 Building Isolator Valve FCO-31A-238 Smoke Removal Fan Circuit Reactor Lower Compartment Cooler Fan Shutdown Board Room A Pressurizing Fan Control Rod Drive Mechanism Cooler Fan As requested in item 2 of the bulletin, TVA is establishing a test program to verify that the actual installed instrumentation and controls are consistent with the drawings reviewed for item 1. TVA is in the process of preparing a scoping document that will allow the required tests to be performed. The testing is expected to be completed by August 1, 1980.

TVA has initiated the paperwork required to allow modification and redesign j of existing circuits so they will remain in the emergency mode after reset of the ESF signal as required ty item 3 of the bulletin.

TVA will submit monthly progress reports on these tests and design changes.

until the requirements of the bulletin are met.

.  : . -- i . . . - . .-

o

--